A Fusion Nuclear Science Facility for a fast-track path to DEMO
Abstract
An accelerated fusion energy development program, a “fast-track” approach, requires developing an understanding of fusion nuclear science (FNS) in parallel with research on ITER to study burning plasmas. A Fusion Nuclear Science Facility (FNSF) in parallel with ITER provides the capability to resolve FNS feasibility issues related to power extraction, tritium fuel sustainability, and reliability, and to begin construction of DEMO upon the achievement of Q~10 in ITER. Fusion nuclear components, including the first wall (FW)/blanket, divertor, heating/fueling systems, etc. are complex systems with many inter-related functions and different materials, fluids, and physical interfaces. These in-vessel nuclear components must operate continuously and reliably with: (a) Plasma exposure, surface particle & radiation loads, (b) High energy 2 neutron fluxes and their interactions in materials (e.g. peaked volumetric heating with steep gradients, tritium production, activation, atomic displacements, gas production, etc.), (c) Strong magnetic fields with temporal and spatial variations (electromagnetic coupling to the plasma including off-normal events like disruptions), and (d) a High temperature, high vacuum, chemically active environment. While many of these conditions and effects are being studied with separate and multiple effect experimental test stands and modeling, fusion nuclear conditions cannot be completely simulated outside the fusion environment. This meansmore »
- Authors:
-
- General Atomics, La Jolla, CA (United States)
- University of California, Los Angeles
- University of Wisconsin Madison
- Publication Date:
- Research Org.:
- General Atomics, San Diego, CA (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1358207
- Grant/Contract Number:
- FC02-04ER54698
- Resource Type:
- Journal Article: 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
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, A.. 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, A.. 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, A.. 2014.
"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, A.},
abstractNote = {An accelerated fusion energy development program, a “fast-track” approach, requires developing an understanding of fusion nuclear science (FNS) in parallel with research on ITER to study burning plasmas. A Fusion Nuclear Science Facility (FNSF) in parallel with ITER provides the capability to resolve FNS feasibility issues related to power extraction, tritium fuel sustainability, and reliability, and to begin construction of DEMO upon the achievement of Q~10 in ITER. Fusion nuclear components, including the first wall (FW)/blanket, divertor, heating/fueling systems, etc. are complex systems with many inter-related functions and different materials, fluids, and physical interfaces. These in-vessel nuclear components must operate continuously and reliably with: (a) Plasma exposure, surface particle & radiation loads, (b) High energy 2 neutron fluxes and their interactions in materials (e.g. peaked volumetric heating with steep gradients, tritium production, activation, atomic displacements, gas production, etc.), (c) Strong magnetic fields with temporal and spatial variations (electromagnetic coupling to the plasma including off-normal events like disruptions), and (d) a High temperature, high vacuum, chemically active environment. While many of these conditions and effects are being studied with separate and multiple effect experimental test stands and modeling, fusion nuclear conditions cannot be completely simulated outside the fusion environment. This means there are many new multi-physics, multi-scale phenomena and synergistic effects yet to be discovered and accounted for in the understanding, design and operation of fusion as a self-sustaining, energy producing system, and significant experimentation and operational experience in a true fusion environment is an essential requirement. In the following sections we discuss the FNSF objectives, describe the facility requirements and a facility concept and operation approach that can accomplish those objectives, and assess the readiness to construct with respect to several key FNSF issues: materials, steady-state operation, disruptions, power exhaust, and breeding blanket. Finally we present our conclusions.},
doi = {10.1016/j.fusengdes.2014.03.055},
url = {https://www.osti.gov/biblio/1358207},
journal = {Fusion Engineering and Design},
issn = {0920-3796},
number = 7-8,
volume = 89,
place = {United States},
year = {2014},
month = {10}
}
Web of Science
Works referenced in this record:
Physics Basis of a Fusion Development Facility Utilizing the Tokamak Approach
journal, January 2010
- Chan, V. S.; Stambaugh, R. D.; Garofalo, A. M.
- Fusion Science and Technology, Vol. 57, Issue 1
Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a Component Testing Facility
journal, August 2009
- Peng, Y. K. M.; Burgess, T. W.; Carroll, A. J.
- Fusion Science and Technology, Vol. 56, Issue 2
Access to sustained high-beta with internal transport barrier and negative central magnetic shear in DIII-D
journal, May 2006
- Garofalo, A. M.; Doyle, E. J.; Ferron, J. R.
- Physics of Plasmas, Vol. 13, Issue 5
Assessment of neutron irradiation effects on RAFM steels
journal, March 2013
- Gaganidze, Ermile; Aktaa, Jarir
- Fusion Engineering and Design, Vol. 88, Issue 3
Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET
journal, July 2013
- van Rooij, G. J.; Coenen, J. W.; Aho-Mantila, L.
- Journal of Nuclear Materials, Vol. 438
Achievement of high fusion triple product, steady-state sustainment and real-time NTM stabilization in high- p ELMy H-mode discharges in JT-60U
journal, October 2003
- Isayama, A.; Kamada, Y.; Hayashi, N.
- Nuclear Fusion, Vol. 43, Issue 10
Overview of JT-60U progress towards steady-state advanced tokamak
journal, September 2005
- Ide, S.; Team, the JT-60
- Nuclear Fusion, Vol. 45, Issue 10
Progress toward fully noninductive, high beta conditions in DIII-D
journal, May 2006
- Murakami, M.; Wade, M. R.; Greenfield, C. M.
- Physics of Plasmas, Vol. 13, Issue 5
Detection of disruptions in the high- β spherical torus NSTX
journal, May 2013
- Gerhardt, S. P.; Darrow, D. S.; Bell, R. E.
- Nuclear Fusion, Vol. 53, Issue 6
Results of the JET real-time disruption predictor in the ITER-like wall campaigns
journal, October 2013
- Vega, Jesús; Dormido-Canto, Sebastián; López, Juan M.
- Fusion Engineering and Design, Vol. 88, Issue 6-8
Graphite Tile Thermal Performance on the New DIII-D Lower Divertor
journal, October 2007
- Murphy, C. J.; Anderson, P. M.; Lasnier, C. J.
- Fusion Science and Technology, Vol. 52, Issue 3
Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER
journal, August 2013
- Eich, T.; Leonard, A. W.; Pitts, R. A.
- Nuclear Fusion, Vol. 53, Issue 9
Optimized tokamak power exhaust with double radiative feedback in ASDEX Upgrade
journal, November 2012
- Kallenbach, A.; Bernert, M.; Eich, T.
- Nuclear Fusion, Vol. 52, Issue 12
Neutronics Analysis in Support of the Fusion Development Facility Design Evolution
journal, August 2011
- Sawan, M. E.; Ibrahim, A. M.; Wilson, P. P. H.
- Fusion Science and Technology, Vol. 60, Issue 2
Works referencing / citing this record:
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
Evaluation of CFETR as a Fusion Nuclear Science Facility using multiple system codes
journal, January 2015
- Chan, V. S.; Costley, A. E.; Wan, B. N.
- Nuclear Fusion, Vol. 55, Issue 2
Effects of fast ions produced by ICRF heating on the pressure at EAST
journal, November 2019
- Zheng, Zhen; Xiang, Nong; Yang, Cheng
- Plasma Science and Technology, Vol. 22, Issue 2
Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade
journal, April 2019
- Tobita, Kenji; Hiwatari, Ryoji; Sakamoto, Yoshiteru
- Fusion Science and Technology, Vol. 75, Issue 5
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