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Title: Fusion Nuclear Science Facilities and Pilot Plants Based on the Spherical Tokamak

Abstract

A Fusion Nuclear Science Facility (FNSF) could play an important role in the development of fusion energy by providing the nuclear environment needed to develop fusion materials and components. The spherical torus/tokamak (ST) is a leading candidate for an FNSF due to its potentially high neutron wall loading and modular configuration. A key consideration for the choice of FNSF configuration is the range of achievable missions as a function of device size. Possible missions include: providing high neutron wall loading and fluence, demonstrating tritium self-sufficiency, and demonstrating electrical self-sufficiency. All of these missions must also be compatible with a viable divertor, first-wall, and blanket solution. ST-FNSF configurations have been developed simultaneously incorporating for the first time: (1) a blanket system capable of tritium breeding ratio TBR approximately 1, (2) a poloidal field coil set supporting high elongation and triangularity for a range of internal inductance and normalized beta values consistent with NSTX/NSTX-U previous/planned operation, (3) a long-legged divertor analogous to the MAST-U divertor which substantially reduces projected peak divertor heat-flux and has all outboard poloidal field coils outside the vacuum chamber and superconducting to reduce power consumption, and (4) a vertical maintenance scheme in which blanket structures and the centerstackmore » can be removed independently. Progress in these ST-FNSF missions vs. configuration studies including dependence on plasma major radius R0 for a range 1m to 2.2m are described. In particular, it is found the threshold major radius for TBR = 1 is R0 greater than or equal to 1.7m, and a smaller R0=1m ST device has TBR approximately 0.9 which is below unity but substantially reduces T consumption relative to not breeding. Calculations of neutral beam heating and current drive for non-inductive ramp-up and sustainment are described. An A=2, R0=3m device incorporating high-temperature superconductor toroidal field coil magnets capable of high neutron fluence and both tritium and electrical self-sufficiency is also presented following systematic aspect ratio studies.« less

Authors:
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  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Publication Date:
DOE Contract Number:  
AC02-09CH11466
Product Type:
Dataset
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Fusion nuclear science facility Pilot plant Spherical tokamak Tritium breeding Negative neutral beams Super-X divertor High-temperature superconductors
Keywords:
Fusion nuclear science facility Pilot plant Spherical tokamak Tritium breeding Negative neutral beams Super-X divertor High-temperature superconductors
OSTI Identifier:
1366722
DOI:
10.11578/1366722

Citation Formats

Menard, J.E., Brown, T., El-Guebaly, L., Boyer, M., Canik, J., Colling, B., Raman, R., Wang, Z., Zhai, Y., Buxton, P., Covele, B., D'Angelo, C., Davis, A., Gerhardt, S., Gryaznevich, M., Harb, M., Hender, T.C., Kaye, S., Kingham, D., Kotschenreuther, M., Mahajan, S., Maingi, R., Marriott, E., Meier, E.T., Mynsberge, L., Neumeyer, C., Ono, M., Park, J.-K., Sabbagh, S.A., Soukhanovskii, V., Valanju, P., and Woolley, R. Fusion Nuclear Science Facilities and Pilot Plants Based on the Spherical Tokamak. United States: N. p., 2016. Web. doi:10.11578/1366722.
Menard, J.E., Brown, T., El-Guebaly, L., Boyer, M., Canik, J., Colling, B., Raman, R., Wang, Z., Zhai, Y., Buxton, P., Covele, B., D'Angelo, C., Davis, A., Gerhardt, S., Gryaznevich, M., Harb, M., Hender, T.C., Kaye, S., Kingham, D., Kotschenreuther, M., Mahajan, S., Maingi, R., Marriott, E., Meier, E.T., Mynsberge, L., Neumeyer, C., Ono, M., Park, J.-K., Sabbagh, S.A., Soukhanovskii, V., Valanju, P., & Woolley, R. Fusion Nuclear Science Facilities and Pilot Plants Based on the Spherical Tokamak. United States. doi:10.11578/1366722.
Menard, J.E., Brown, T., El-Guebaly, L., Boyer, M., Canik, J., Colling, B., Raman, R., Wang, Z., Zhai, Y., Buxton, P., Covele, B., D'Angelo, C., Davis, A., Gerhardt, S., Gryaznevich, M., Harb, M., Hender, T.C., Kaye, S., Kingham, D., Kotschenreuther, M., Mahajan, S., Maingi, R., Marriott, E., Meier, E.T., Mynsberge, L., Neumeyer, C., Ono, M., Park, J.-K., Sabbagh, S.A., Soukhanovskii, V., Valanju, P., and Woolley, R. 2016. "Fusion Nuclear Science Facilities and Pilot Plants Based on the Spherical Tokamak". United States. doi:10.11578/1366722. https://www.osti.gov/servlets/purl/1366722. Pub date:Sat Oct 01 00:00:00 EDT 2016
@article{osti_1366722,
title = {Fusion Nuclear Science Facilities and Pilot Plants Based on the Spherical Tokamak},
author = {Menard, J.E. and Brown, T. and El-Guebaly, L. and Boyer, M. and Canik, J. and Colling, B. and Raman, R. and Wang, Z. and Zhai, Y. and Buxton, P. and Covele, B. and D'Angelo, C. and Davis, A. and Gerhardt, S. and Gryaznevich, M. and Harb, M. and Hender, T.C. and Kaye, S. and Kingham, D. and Kotschenreuther, M. and Mahajan, S. and Maingi, R. and Marriott, E. and Meier, E.T. and Mynsberge, L. and Neumeyer, C. and Ono, M. and Park, J.-K. and Sabbagh, S.A. and Soukhanovskii, V. and Valanju, P. and Woolley, R.},
abstractNote = {A Fusion Nuclear Science Facility (FNSF) could play an important role in the development of fusion energy by providing the nuclear environment needed to develop fusion materials and components. The spherical torus/tokamak (ST) is a leading candidate for an FNSF due to its potentially high neutron wall loading and modular configuration. A key consideration for the choice of FNSF configuration is the range of achievable missions as a function of device size. Possible missions include: providing high neutron wall loading and fluence, demonstrating tritium self-sufficiency, and demonstrating electrical self-sufficiency. All of these missions must also be compatible with a viable divertor, first-wall, and blanket solution. ST-FNSF configurations have been developed simultaneously incorporating for the first time: (1) a blanket system capable of tritium breeding ratio TBR approximately 1, (2) a poloidal field coil set supporting high elongation and triangularity for a range of internal inductance and normalized beta values consistent with NSTX/NSTX-U previous/planned operation, (3) a long-legged divertor analogous to the MAST-U divertor which substantially reduces projected peak divertor heat-flux and has all outboard poloidal field coils outside the vacuum chamber and superconducting to reduce power consumption, and (4) a vertical maintenance scheme in which blanket structures and the centerstack can be removed independently. Progress in these ST-FNSF missions vs. configuration studies including dependence on plasma major radius R0 for a range 1m to 2.2m are described. In particular, it is found the threshold major radius for TBR = 1 is R0 greater than or equal to 1.7m, and a smaller R0=1m ST device has TBR approximately 0.9 which is below unity but substantially reduces T consumption relative to not breeding. Calculations of neutral beam heating and current drive for non-inductive ramp-up and sustainment are described. An A=2, R0=3m device incorporating high-temperature superconductor toroidal field coil magnets capable of high neutron fluence and both tritium and electrical self-sufficiency is also presented following systematic aspect ratio studies.},
doi = {10.11578/1366722},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {10}
}

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Works referenced in this record:

Fusion nuclear science facilities and pilot plants based on the spherical tokamak
journal, August 2016


    Works referencing / citing this record:

    Fusion nuclear science facilities and pilot plants based on the spherical tokamak
    journal, August 2016


    Fusion nuclear science facilities and pilot plants based on the spherical tokamak
    journal, August 2016