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On energy confinement following the onset of ‘stiff’ transport

Published online by Cambridge University Press:  06 March 2020

J. W. Connor*
Affiliation:
CCFE, Culham Science Centre, Abingdon, Oxon OX 14 3DB, UK Department of Physics, Imperial College of Science and Technology and Medicine, London SW7 2BZ, UK
R. J. Hastie
Affiliation:
CCFE, Culham Science Centre, Abingdon, Oxon OX 14 3DB, UK
K. Richards
Affiliation:
CCFE, Culham Science Centre, Abingdon, Oxon OX 14 3DB, UK Department of Physics and Astronomy, University College London, Gower Street,London WC1E 6BT, UK
*
†Email address for correspondence: jack.connor@ukaea.uk
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Abstract

The dependence of confinement on input power for a tokamak plasma with regions having a stiff temperature profile is explored. The resilience of the confinement of the core energy to increasing power loss by core radiation from impurities in such situations, as it is anticipated will be required in a demonstration fusion reactor (DEMO) design, is examined.

Information

Type
Research Article
Copyright
© Cambridge University Press 2020
Figure 0

Figure 1. Schematic diagrams showing the values of $\unicode[STIX]{x1D706}$ when they reach a critical value for the onset of a stiff temperature profile, as a function of plasma radius, $\unicode[STIX]{x1D70C}$. (a) case (i); (b) case (ii); sub-case a; and (c) case (ii) sub-case b. The dashed horizontal lines separate the different zones of $\unicode[STIX]{x1D706}$ used in calculating $F$, as defined in the text, leading to differing numbers of intersections as $\unicode[STIX]{x1D706}$ increases. The critical radius, $\unicode[STIX]{x1D70C}_{\ast }$ is given later in (3.29).

Figure 1

Figure 2. The variation of $\unicode[STIX]{x1D70C}_{\ast }$ with ${\hat{c}}$; it is compared with $\unicode[STIX]{x1D70C}_{0}=0.3$ as an example.

Figure 2

Figure 3. The variation of the function $F(\hat{\unicode[STIX]{x1D706}},\widehat{c},\unicode[STIX]{x1D70C}_{0})$, normalised to the asymptotic value, $F_{\infty }$, characterising the plasma energy content, for the constant $\unicode[STIX]{x1D712}$ case, as a function of $\unicode[STIX]{x1D706}/2{\hat{c}}$, representing the power dependence. $\unicode[STIX]{x1D70C}_{0}=0.33$, 0.66 and 1.0, ranging from more centrally localised heating to being constant in radius. ${\hat{c}}=1.375$, 2.75 and 4.125 covering the range of critical gradients and aspect ratios from conventional tokamaks to spherical tokamaks.

Figure 3

Figure 4. As for figure 3, but for the gyro-Bohm model and in terms of $\overline{\unicode[STIX]{x1D706}}$, with the corresponding values $\overline{c}=3.438$, 6.875 and 10.313.

Figure 4

Figure 5. The convergence of $F(\hat{\unicode[STIX]{x1D706}},\widehat{c},\unicode[STIX]{x1D70C}_{0})$ to an asymptotic form for a sequence of values of $\unicode[STIX]{x1D70C}_{0}$ approaching zero ($\unicode[STIX]{x1D70C}_{0}=1.0\rightarrow 0.01$) for the constant $\unicode[STIX]{x1D712}$ model with ${\hat{c}}=1.375$.

Figure 5

Figure 6. The effect of the $\unicode[STIX]{x1D712}$ profile parameter, $\unicode[STIX]{x1D6FC}$, of the improved gyro-Bohm model on the plasma energy content $F$ for $\unicode[STIX]{x1D70C}_{0}=0.45$ and $\overline{c}=6.875$ with $\unicode[STIX]{x1D6FC}=1$, and 2. The simple gyro-Bohm case ($\unicode[STIX]{x1D6FC}=0$) and the constant $\unicode[STIX]{x1D712}$ case (for the same value of $c$) are shown for comparison.

Figure 6

Figure 7. The evolution of $\unicode[STIX]{x1D70C}_{1,2,3}(\hat{\unicode[STIX]{x1D706}})$, the radii where the transitions to ‘stiff’ transport occur, as functions of the parameter $\hat{\unicode[STIX]{x1D706}}$, representing the net heating power for the case of a constant thermal diffusivity. (a) $\unicode[STIX]{x1D70C}_{0}=0.6$, ${\hat{c}}=2.75$ represents case (i); (b) $\unicode[STIX]{x1D70C}_{0}=0.25$, ${\hat{c}}=2.75$ represents case (iia); (c) $\unicode[STIX]{x1D70C}_{0}=0.3$, ${\hat{c}}=1.75$ represents case (iib).

Figure 7

Figure 8. Allowed fraction of impurity radiative power, $\unicode[STIX]{x1D6FE}=P_{\text{Rad}}/P_{\text{H}}$ before plasma energy content $F(\overline{\unicode[STIX]{x1D706}},\overline{c},\unicode[STIX]{x1D70C}_{0})$ falls to 90 % of its value as a function of $\overline{\unicode[STIX]{x1D706}}_{\text{H}}$, which corresponds to the heating power $P_{\text{H}}$, in the case of the gyro-Bohm model: $\unicode[STIX]{x1D70C}_{0}=0.33$ and $\unicode[STIX]{x1D70C}_{0}=0.66$, with $\overline{c}=3.438$, 6.875 and 10.312.

Figure 8

Figure 9. The effect of the impurity radiation fraction$,\unicode[STIX]{x1D6FE}=P_{\text{Rad}}/P_{\text{H}}$, on the normalised energy content, $F(\overline{\unicode[STIX]{x1D706}},\overline{c},\unicode[STIX]{x1D70C}_{0})$, with $\overline{\unicode[STIX]{x1D706}}_{\text{H}}$, representing the heating power, $P_{\text{H}}$, and $\overline{\unicode[STIX]{x1D706}}=\overline{\unicode[STIX]{x1D706}}_{\text{H}}(1-\unicode[STIX]{x1D6FE})$ representing the net heating allowing for impurity radiation, for the gyro-Bohm model with $\overline{c}=6.875$ and $\unicode[STIX]{x1D6FE}=0,0.2,0.7$ and 0.9 for: (a) $\unicode[STIX]{x1D70C}_{0}=0.33$ and (b) $\unicode[STIX]{x1D70C}_{0}=0.66$.

Figure 9

Figure 10. Comparisons of the fit function (6.3) for $F(\overline{\unicode[STIX]{x1D706}}/2\overline{c},\overline{c},\unicode[STIX]{x1D70C}_{0})$ with the numerical results for the gyro-Bohm mode for $\unicode[STIX]{x1D70C}_{0}=0.33,0.66$ and 1.0, with $\overline{c}=3.438$, 6.875 and 10.313. The values of $\unicode[STIX]{x1D70C}_{0}$ are common in each column and increase from left to right and the values of $\overline{c}$ are common in each row and increase from top to bottom.

Figure 10

Figure 11. The variation of the coefficients $a$ and $b$ used in the fitting function (6.2) with $\unicode[STIX]{x1D70C}_{0}$ for $\overline{c}=3.438$, 6.875 and 10.313. The left-hand column is for (a), the middle column for (b) and the right-hand column shows the mean square error in the fits. The values of $\overline{c}$ are common in each row and increase from top to bottom.