Tokamak and RFP ignition requirements

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A plasma model is applied to calculate numerically transport- confinement (n{tau}{sub E}) requirements and steady-state operation tokamak. The CIT tokamak and RFP ignition conditions are examined. Physics differences between RFP and tokamaks, and their consequences for a DT ignition machine, are discussed. The ignition RFP, compared to a tokamak, has many physics advantages, including ohmic heating to ignition (no need for auxiliary heating systems), higher beta, low ignition current, less sensitivity of ignition requirements to impurity effects, no hard disruptions (associated with beta or density limits), and successful operation with high radiation fractions (f{sub RAD} {approximately} 0.95). These physics advantages, ... continued below

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Pages: (6 p)

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Werley, K.A. January 1, 1991.

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Description

A plasma model is applied to calculate numerically transport- confinement (n{tau}{sub E}) requirements and steady-state operation tokamak. The CIT tokamak and RFP ignition conditions are examined. Physics differences between RFP and tokamaks, and their consequences for a DT ignition machine, are discussed. The ignition RFP, compared to a tokamak, has many physics advantages, including ohmic heating to ignition (no need for auxiliary heating systems), higher beta, low ignition current, less sensitivity of ignition requirements to impurity effects, no hard disruptions (associated with beta or density limits), and successful operation with high radiation fractions (f{sub RAD} {approximately} 0.95). These physics advantages, coupled with important engineering advantages associated with lower external magnetic fields, larger aspect ratios, and smaller plasma cross sections translate into significant cost reductions for both ignition and power reactor. The primary drawback of the RFP is the uncertainty that the present confinement scaling will extrapolate to reactor regimes. The 4-MA ZTH was expected to extend the n{tau}{sub E} transport scaling data three order of magnitude above ZT-40M results, and if the present scaling held, to achieve a DT-equivalent scientific energy breakeven, Q=1. A basecase RFP ignition point is identified with a plasma current of 8.1 MA and no auxiliary heating. 16 refs., 4 figs., 1 tab.

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Pages: (6 p)

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OSTI; NTIS; INIS; GPO Dep.

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  • 14. IEEE symposium on fusion engineering, San Diego, CA (United States), 30 Sep - 3 Oct 1991

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  • Other: DE92002364
  • Report No.: LA-UR-91-3217
  • Report No.: CONF-910968--36
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5071547
  • Archival Resource Key: ark:/67531/metadc1058425

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  • January 1, 1991

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  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 7:06 p.m.

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Werley, K.A. Tokamak and RFP ignition requirements, article, January 1, 1991; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1058425/: accessed October 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.