- Main
Higher fusion power gain with profile control in DIII-D tokamak plasmas
- Lazarus, EA;
- Navratil, GA;
- Greenfield, CM;
- Strait, EJ;
- Austin, ME;
- Burrell, KH;
- Casper, TA;
- Baker, DR;
- DeBoo, JC;
- Doyle, EJ;
- Durst, RD;
- Ferron, JR;
- Forest, CB;
- Gohil, P;
- Groebner, RJ;
- Heidbrink, WW;
- Hong, R;
- Howald, AW;
- Hsieh, C-L;
- Hyatt, AW;
- Jackson, GL;
- Kim, J;
- Lao, LL;
- Lanier, CJ;
- Leonard, AW;
- Lohr, JM;
- La Haye, RJ;
- Maingi, R;
- Miller, RL;
- Murakami, M;
- Osborne, TH;
- Perkins, LJ;
- Petty, CC;
- Rettig, CL;
- Rhodes, TL;
- Rice, BW;
- Sabbagh, SA;
- Schissel, DP;
- Scoville, JT;
- Snider, RT;
- Stallard, BW;
- Stambaugh, RD;
- St. John, HE;
- Stockdale, RE;
- Taylor, PL;
- Taylor, TS;
- Thomas, DM;
- Turnbull, AD;
- Wade, MR;
- Wood, RD;
- Whye, DG
Abstract
Strong shaping, favourable for stability and improved energy confinement, together with a significant expansion of the central region of improved confinement in negative central magnetic shear target plasmas, increased the maximum fusion power produced in DIII-D by a factor of 3. Using deuterium plasmas, the highest fusion power gain, the ratio of fusion power to input power, Q, was 0.0015, corresponding to an equivalent Q of 0.32 in a deuterium-tritium plasma, which is similar to values achieved in tokamaks of larger size and magnetic field. A simple transformation relating Q to the stability parameters is presented.
Many UC-authored scholarly publications are freely available on this site because of the UC's open access policies. Let us know how this access is important for you.
Main Content
Enter the password to open this PDF file:
-
-
-
-
-
-
-
-
-
-
-
-
-
-