Magnet design considerations for Fusion Nuclear Science Facility

Zhai, Yuhu; Kessel, Chuck; El-guebaly, Laila; Titus, Peter

doi:10.1109/TASC.2016.2532921

Title: Magnet design considerations for Fusion Nuclear Science Facility

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Abstract

The Fusion Nuclear Science Facility (FNSF) is a nuclear confinement facility to provide a fusion environment with components of the reactor integrated together to bridge the technical gaps of burning plasma and nuclear science between ITER and the demonstration power plant (DEMO). Compared to ITER, the FNSF is smaller in size but generates much higher magnetic field, 30 times higher neutron fluence with 3 orders of magnitude longer plasma operation at higher operating temperatures for structures surrounding the plasma. Input parameters to the magnet design from system code analysis include magnetic field of 7.5 T at the plasma center with plasma major radius of 4.8 m and minor radius of 1.2 m, and a peak field of 15.5 T on the TF coils for FNSF. Both low temperature superconductor (LTS) and high temperature superconductor (HTS) are considered for the FNSF magnet design based on the state-of-the-art fusion magnet technology. The higher magnetic field can be achieved by using the high performance ternary Restack Rod Process (RRP) Nb3Sn strands for toroidal field (TF) magnets. The circular cable-in-conduit conductor (CICC) design similar to ITER magnets and a high aspect ratio rectangular CICC design are evaluated for FNSF magnets but low activation jacketmore »« less

Authors:

Zhai, Yuhu ^[1]; Kessel, Chuck ^[1]; El-guebaly, Laila ^[2]; Titus, Peter ^[1]

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Univ. of Wisconsin, Madison, WI (United States)

Publication Date:: Thu Feb 25 00:00:00 EST 2016

Research Org.:: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1239593

Report Number(s):: PPPL-5206
Journal ID: ISSN 1051-8223; TRN: US1600635

Grant/Contract Number:: AC02-09CH11466

Resource Type:: Accepted Manuscript

Journal Name:: IEEE Transactions on Applied Superconductivity

Additional Journal Information:: Journal Volume: 06; Journal Issue: 12; Journal ID: ISSN 1051-8223

Publisher:: Institute of Electrical and Electronics Engineers (IEEE)

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; next step fusion reactors; superconducting fusion magnet design; cable-in-conduit conductors; material radiation limits

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                    Zhai, Yuhu, Kessel, Chuck, El-guebaly, Laila, and Titus, Peter. Magnet design considerations for Fusion Nuclear Science Facility.  United States: N. p., 2016. 
Web.  doi:10.1109/TASC.2016.2532921.

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                    Zhai, Yuhu, Kessel, Chuck, El-guebaly, Laila, & Titus, Peter. Magnet design considerations for Fusion Nuclear Science Facility.  United States.  https://doi.org/10.1109/TASC.2016.2532921

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                    Zhai, Yuhu, Kessel, Chuck, El-guebaly, Laila, and Titus, Peter. Thu .  
"Magnet design considerations for Fusion Nuclear Science Facility".  United States.  https://doi.org/10.1109/TASC.2016.2532921.  https://www.osti.gov/servlets/purl/1239593.

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@article{osti_1239593,

  title        = {Magnet design considerations for Fusion Nuclear Science Facility},

  author       = {Zhai, Yuhu and Kessel, Chuck and El-guebaly, Laila and Titus, Peter},

  abstractNote = {The Fusion Nuclear Science Facility (FNSF) is a nuclear confinement facility to provide a fusion environment with components of the reactor integrated together to bridge the technical gaps of burning plasma and nuclear science between ITER and the demonstration power plant (DEMO). Compared to ITER, the FNSF is smaller in size but generates much higher magnetic field, 30 times higher neutron fluence with 3 orders of magnitude longer plasma operation at higher operating temperatures for structures surrounding the plasma. Input parameters to the magnet design from system code analysis include magnetic field of 7.5 T at the plasma center with plasma major radius of 4.8 m and minor radius of 1.2 m, and a peak field of 15.5 T on the TF coils for FNSF. Both low temperature superconductor (LTS) and high temperature superconductor (HTS) are considered for the FNSF magnet design based on the state-of-the-art fusion magnet technology. The higher magnetic field can be achieved by using the high performance ternary Restack Rod Process (RRP) Nb3Sn strands for toroidal field (TF) magnets. The circular cable-in-conduit conductor (CICC) design similar to ITER magnets and a high aspect ratio rectangular CICC design are evaluated for FNSF magnets but low activation jacket materials may need to be selected. The conductor design concept and TF coil winding pack composition and dimension based on the horizontal maintenance schemes are discussed. Neutron radiation limits for the LTS and HTS superconductors and electrical insulation materials are also reviewed based on the available materials previously tested. As a result, the material radiation limits for FNSF magnets are defined as part of the conceptual design studies for FNSF magnets.},

  doi          = {10.1109/TASC.2016.2532921},

  journal      = {IEEE Transactions on Applied Superconductivity},

  number       = 12,

  volume       = 06,

  place        = {United States},

  year         = {Thu Feb 25 00:00:00 EST 2016},

  month        = {Thu Feb 25 00:00:00 EST 2016}

}

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