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33b9215
Initial commit, added heating separation
chris-ashe a03b295
lower hybrid fenstermacher first addition
chris-ashe 8583ee6
All LHCD pages added
chris-ashe a85bfd5
quick fix main page
chris-ashe 410c9cb
added overview pages from RF heating types
chris-ashe 6620dd9
Main H&CD page updated for fixed heating
chris-ashe a913cf3
RF and NBI pages separated
chris-ashe 5379ad9
created separate H&CD images folder
chris-ashe e7c93e3
All RF pages added
chris-ashe 4e42e55
all model pages added
chris-ashe 6571485
HARE obsolete, remove model page
chris-ashe 0c5663e
ecrh_gamma page filled in
chris-ashe b1cc847
beam stopping mode added
chris-ashe 7752843
cfnbi addition
chris-ashe e2429a0
coloumb log and first couple attempt
chris-ashe 268e382
iter nbi model first draft
chris-ashe 82c42a1
legendre polynomial
chris-ashe dcfe611
Merge branch 'main' into 2998-update-heating-and-current-drive-docume…
chris-ashe be597cd
Added cutoff ecrh model page to docs
chris-ashe 5190c73
rf overview text
chris-ashe 47f51bf
Merge commit '5190c73ee3f8c657939c8ff0745384b113faaa0f' into update_h…
chris-ashe 633fe43
docs update
chris-ashe 25ed344
ebw changes
chris-ashe a301827
nbi overview update
chris-ashe 57c393b
culham nb model
chris-ashe 2e5b22a
Update NBI overview
chris-ashe 246d3d5
Update ITER Neutral Beam Model documentation
chris-ashe 3c69d86
Update Culham Neutral Beam Model documentation
chris-ashe 99d68a1
Update Culham Lower Hybrid
chris-ashe f4f47c8
Update ECRH User Input Gamma Model
chris-ashe 5b3c78e
docs: Update ion cyclotron heating documentation
chris-ashe 1daa559
docs: Update NBI documentation with ion mass and electron density cha…
chris-ashe f86fa72
Minor fix to HCD overview
j-a-foster 8999e16
docs: Update NBI documentation with ion mass and electron density cha…
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223
documentation/proc-pages/eng-models/heating_and_current_drive/NBI/culham_nb.md
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| # Culham Neutral Beam Model | `culnbi()` | ||
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| - `iefrf/iefrffix` = 8 | ||
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| This routine calculates Neutral Beam current drive parameters | ||
| using the corrections outlined in AEA FUS 172 to the ITER method. | ||
| The result cannot be guaranteed for devices with aspect ratios far | ||
| from that of ITER (approx. 2.8). | ||
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| | Output | Description | | ||
| |----------|-------------| | ||
| | $\mathtt{effnbss}$ | Neutral beam current drive efficiency in Amperes per Watt | | ||
| | $\mathtt{fpion}$ | Fraction of NB power given to ions | | ||
| | $\mathtt{fshine}$ | Shine-through fraction of the beam | | ||
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| $$ | ||
| \mathtt{frbeam} = \frac{R_{\text{tan}}}{R_0} | ||
| $$ | ||
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| Where $R_{\text{tan}}$ is major radius at which the centre-line of the beam is tangential to the toroidal direction. This can be user defined | ||
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| $$ | ||
| \left(1+ \frac{1}{A}\right) < \mathtt{frbeam} | ||
| $$ | ||
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| A quick sanity check is done to make sure no negative roots are formed when calculating $\mathtt{dpath}$ this prevents setups where the NBI beam would miss the plasma | ||
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| $$ | ||
| \mathtt{dpath} = R_0 \sqrt{\left(1+\frac{1}{A}\right)^2-\mathtt{frbeam}^2} | ||
| $$ | ||
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| Beams topping cross section is calculated via $\mathtt{sigbeam}$ found [here](../NBI/nbi_overview.md/#beam-stopping-cross-section-sigbeam). This produces $\mathtt{sigstop}$ | ||
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| Calculate number of decay lengths to centre | ||
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| $$ | ||
| \mathtt{taubeam} = \mathtt{dpath} \times n_{\text{e,0}} \times \mathtt{sigstop} | ||
| $$ | ||
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| Calculate the shine through fraction of the beam | ||
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| $$ | ||
| \mathtt{fshine} = e^{\left(-2 \times \mathtt{dpath} \times n_{\text{e,0}} \times \mathtt{sigstop}\right)} | ||
| $$ | ||
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| Deuterium and tritium beam densities | ||
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| $$ | ||
| \mathtt{dend} = n_{\text{ion}} \times (1-\mathtt{ftritbm}) | ||
| $$ | ||
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| $$ | ||
| \mathtt{dent} = n_{\text{ion}} \times \mathtt{ftritbm} | ||
| $$ | ||
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| Power split to the ions and electrons is clauclated with the $\mathtt{cfnbi()}$ method found [here](../NBI/nbi_overview.md/#ion-coupled-power-cfnbi) and outputs $\mathtt{fpion}$ | ||
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| ## Current drive efficiency | `etanb2()` | ||
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| This routine calculates the current drive efficiency in A/W of | ||
| a neutral beam system, based on the 1990 ITER model, | ||
| plus correction terms outlined in Culham Report AEA FUS 172. | ||
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| | Input | Description | | ||
| | :---------- | :----------------------------------- | | ||
| | $\mathtt{abeam}$ | beam ion mass (amu) | | ||
| | $\mathtt{alphan}$, $\alpha_n$ | density profile factor | | ||
| | $\mathtt{alphat}$, $\alpha_T$ | temperature profile factor | | ||
| | $\mathtt{aspect}$, $A$ | aspect ratio | | ||
| | $\mathtt{dene}$, $n_{\text{e}}$ | volume averaged electron density $(\text{m}^{-3})$ | | ||
| | $\mathtt{dnla}$, $n_{\text{e,0}}$ | line averaged electron density $(\text{m}^{-3})$ | | ||
| | $\mathtt{enbeam}$ | neutral beam energy $(\text{keV})$ | | ||
| | $\mathtt{frbeam}$ | R_tangent / R_major for neutral beam injection | | ||
| | $\mathtt{fshine}$ | shine-through fraction of beam | | ||
| | $\mathtt{rmajor}$, $R$ | plasma major radius $(\text{m})$ | | ||
| | $\mathtt{rminor}$, $a$ | plasma minor radius $(\text{m})$ | | ||
| | $\mathtt{ten}$ | density weighted average electron temperature $(\text{keV})$ | | ||
| | $\mathtt{zeff}$, $Z_{\text{eff}}$ | plasma effective charge | | ||
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| Charge of beam ions | ||
| $$ | ||
| \mathtt{zbeam} = 1.0 | ||
| $$ | ||
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| Fitting factor (IPDG89) | ||
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| $$ | ||
| \mathtt{bbd} = 1.0 | ||
| $$ | ||
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| Volume averaged electron density ($10^{20} \text{m}^{-3}$) | ||
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| $$ | ||
| \mathtt{dene20} = n_{\text{e,20}} | ||
| $$ | ||
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| Line averaged electron density ($10^{20} \text{m}^{-3}$) | ||
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| $$ | ||
| \mathtt{dnla20} = n_{\text{(e,0) 20}} | ||
| $$ | ||
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| Critical energy ($\text{MeV}$) (power to electrons = power to ions) (IPDG89) | ||
| N.B. ten is in keV | ||
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| $$ | ||
| \mathtt{ecrit} = 0.01 \times \mathtt{abeam} \times \mathtt{ten} | ||
| $$ | ||
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| Beam energy in MeV | ||
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| $$ | ||
| \mathtt{ebmev} = \frac{\mathtt{enbeam}}{10^3} | ||
| $$ | ||
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| x and y coefficients of function J0(x,y) (IPDG89) | ||
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| $$ | ||
| \mathtt{xjs} = \frac{\mathtt{ebmev}}{\mathtt{bbd}\times \mathtt{ecrit}} | ||
| $$ | ||
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| $$ | ||
| \mathtt{xj} = \sqrt{\mathtt{xjs}} | ||
| $$ | ||
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| $$ | ||
| \mathtt{yj} = \frac{0.8 \times Z_{\text{eff}}}{\mathtt{abeam}} | ||
| $$ | ||
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| Fitting function J0(x,y) | ||
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| $$ | ||
| \mathtt{j0} = \frac{xjs}{(4.0 + 3.0 \times \mathtt{yj} + \mathtt{xjs} \times (\mathtt{xj} + 1.39 + 0.61 \times yj^{0.7}))} | ||
| $$ | ||
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| Effective inverse aspect ratio, with a limit on its maximum value | ||
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| $$ | ||
| \mathtt{epseff} = \text{min}(0.2, (0.5 / A)) | ||
| $$ | ||
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| Reduction in the reverse electron current | ||
| due to neoclassical effects | ||
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| $$ | ||
| \mathtt{gfac} = (1.55 + 0.85 / Z_{\text{eff}}) \times \sqrt{\mathtt{epseff}} - (0.2 + 1.55 / Z_{\text{eff}}) \times \mathtt{epseff} | ||
| $$ | ||
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| Reduction in the net beam driven current | ||
| due to the reverse electron current | ||
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| $$ | ||
| \mathtt{ffac} = 1.0 - \frac{\mathtt{zbeam}}{Z_{\text{eff}}} \times (1.0 - \mathtt{gfac}) | ||
| $$ | ||
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| Normalisation to allow results to be valid for | ||
| non-ITER plasma size and density: | ||
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| Line averaged electron density ($10^{20} \text{m}^{-3}$) normalised to ITER | ||
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| $$ | ||
| \mathtt{nnorm} = 1.0 | ||
| $$ | ||
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| Distance along beam to plasma centre | ||
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| $$ | ||
| \mathtt{r} = \text{max}(R, R \times \mathtt{frbeam}) | ||
| $$ | ||
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| $$ | ||
| \mathtt{eps1} = a / \mathtt{r} | ||
| $$ | ||
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| $$ | ||
| \mathtt{d} = R \times \sqrt{((1.0 + \mathtt{eps1})^2 - \mathtt{frbeam}^2)} | ||
| $$ | ||
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| Distance along beam to plasma centre for ITER | ||
| assuming a tangency radius equal to the major radius | ||
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| $$ | ||
| \mathtt{epsitr} = 2.15 / 6.0 | ||
| $$ | ||
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| $$ | ||
| \mathtt{dnorm} = 6.0 \times \sqrt{(2.0 \times \mathtt{epsitr} + \mathtt{epsitr}^2)} | ||
| $$ | ||
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| Normalisation to beam energy (assumes a simplified formula for | ||
| the beam stopping cross-section) | ||
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| $$ | ||
| \mathtt{ebnorm} = \mathtt{ebmev} \times ((\mathtt{nnorm} \times \mathtt{dnorm}) / (n_{\text{e,0}} \times \mathtt{d})) ^{1.0 / 0.78)} | ||
| $$ | ||
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| A_bd fitting coefficient, after normalisation with ebnorm | ||
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| $$ | ||
| \mathtt{abd} = ( | ||
| 0.107 | ||
| \times (1.0 - 0.35 \times \alpha_n + 0.14 \times \alpha_n^2) | ||
| \times (1.0 - 0.21 \times \alpha_T) | ||
| \times (1.0 - 0.2 \times \mathtt{ebnorm} + 0.09 \times \mathtt{ebnorm}^2) | ||
| ) | ||
| $$ | ||
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| Normalised current drive efficiency ($\text{A/W} \text{m}^{2}$) (IPDG89) | ||
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| $$ | ||
| \mathtt{gamnb} = 5.0 \times \mathtt{abd} \times 0.1 \times \mathtt{ten} \times (1.0 - \mathtt{fshine}) \times \mathtt{frbeam} \times \frac{\mathtt{j0}}{0.2} \times \mathtt{ffac} | ||
| $$ | ||
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| Current drive efficiency (A/W) | ||
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| $$ | ||
| \text{Current drive efficiency [A/W]} = \frac{\mathtt{gamnb}}{\mathtt{dene20}\times R} | ||
| $$ |
128 changes: 128 additions & 0 deletions
128
documentation/proc-pages/eng-models/heating_and_current_drive/NBI/iter_nb.md
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| @@ -0,0 +1,128 @@ | ||
| # ITER Neutral Beam Model | `iternb()` | ||
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| - `iefrf/iefrffix` = 5 | ||
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| | Output | Description | | ||
| |----------|-------------| | ||
| | $\mathtt{effnbss}$ | Neutral beam current drive efficiency in $\text{A/W}$ | | ||
| | $\mathtt{fpion}$ | Fraction of NB power given to ions | | ||
| | $\mathtt{fshine}$ | Shine-through fraction of the beam | | ||
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| This model calculates the current drive parameters for a neutral beam system, based on the 1990 ITER model.[^1] | ||
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| Firstly the beam access is checked for such that | ||
| $$ | ||
| \bigg(1+ \frac{1}{A}\bigg) > (R_{\text{tangential}}/R_0) | ||
| $$ | ||
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| The beam path length to centre is calculated: | ||
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| $$ | ||
| \underbrace{\mathtt{dpath}}_{\text{Path length to centre}} = R_0 \sqrt{\left(\left(1+\frac{1}{A}\right)^2-\mathtt{frbeam}^2\right)} | ||
| $$ | ||
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| Beam stopping cross-section ($\sigma_{\text{beam}}$) is calculated using the `sigbeam` method described [here](nbi_overview.md) : | ||
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| Calculate number of electron decay lengths to centre | ||
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| $$ | ||
| \tau_{\text{beam}} = \mathtt{dpath}\times n_e \sigma_{\text{beam}} | ||
| $$ | ||
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| Shine-through fraction of beam: | ||
| $$ | ||
| f_{\text{shine}} = e^{(-2.0 \times \mathtt{dpath} \times n_e \sigma_{\text{beam}})} \\ | ||
| $$ | ||
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| Deuterium and tritium beam densities: | ||
| $$ | ||
| n_D = n_i * (1.0 - \mathtt{ftritbm}) | ||
| $$ | ||
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| $$ | ||
| n_T = n_i * \mathtt{ftritbm} | ||
| $$ | ||
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| Power split to ions / electrons is calculated via the the `cfnbi` method described [here](nbi_overview.md) | ||
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| ## Current drive efficiency | `etanb()` | ||
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| This routine calculates the current drive efficiency of | ||
| a neutral beam system, based on the 1990 ITER model. | ||
| AEA FUS 251: A User's Guide to the PROCESS Systems Code | ||
| ITER Physics Design Guidelines: 1989 IPDG89, N. A. Uckan et al, | ||
| ITER Documentation Series No.10, IAEA/ITER/DS/10, IAEA, Vienna, 1990 | ||
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| | Input | Description | | ||
| |---------|-----------------------------------------------------------| | ||
| | $\mathtt{abeam}$, $m_{\text{u,ion}}$ | Beam ion mass ($\text{amu}$) | | ||
| | $\mathtt{alphan}$ | Density profile factor | | ||
| | $\mathtt{alphat}$ | Temperature profile factor | | ||
| | $\mathtt{aspect}$, $A$ | Aspect ratio | | ||
| | $\mathtt{dene20}$, $n_{\text{e,20}}$ | Volume averaged electron density ($10^{20} \text{m}^{-3}$) | | ||
| | $\mathtt{ebeam}$ | Neutral beam energy ($\text{keV}$) | | ||
| | $\mathtt{rmajor}$, R | Plasma major radius ($\text{m}$) | | ||
| | $\mathtt{ten}$ | Density weighted average electron temperature ($\text{keV}$) | | ||
| | $\mathtt{zeff}$, $Z_{\text{eff}}$ | Plasma effective charge | | ||
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| | Output | Description | | ||
| |---------|-----------------------------------------------------------| | ||
| | $\mathtt{etanb}$ | Neutral beam current drive efficiency in $\text{A/W}$ | | ||
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| $$ | ||
| \mathtt{zbeam} = 1.0 | ||
| $$ | ||
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| $$ | ||
| \mathtt{bbd} = 1.0 | ||
| $$ | ||
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| Ratio of E_beam/E_crit | ||
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| $$ | ||
| \mathtt{xjs} = \frac{\mathtt{ebeam}}{10 \ m_{\text{u,ion}} \ T_e} | ||
| $$ | ||
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| $$ | ||
| \mathtt{xj} = \sqrt{\mathtt{xjs}} | ||
| $$ | ||
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| $$ | ||
| \mathtt{yj} = 0.8 \frac{Z_{\text{eff}}}{m_{\text{u,ion}}} | ||
| $$ | ||
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| $$ | ||
| \mathtt{rjfunc} = \frac{\mathtt{xjs}}{((4.0 + 3.0\mathtt{yj} + \mathtt{xjs}(\mathtt{xj} + 1.39 + 0.61\mathtt{yj}^{0.7})))} | ||
| $$ | ||
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| $$ | ||
| \mathtt{epseff} = \frac{0.5}{A} | ||
| $$ | ||
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| $$ | ||
| \mathtt{gfac} = \left(1.55 + \frac{0.85}{Z_{\text{eff}}}\right)\left(\sqrt{\mathtt{epseff}}-\left(0.2+\frac{1.55}{Z_{\text{eff}}}\right)\mathtt{epseff}\right) | ||
| $$ | ||
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| $$ | ||
| \mathtt{ffac} = \frac{1}{\mathtt{zbeam}} - \frac{(1-\mathtt{gfac})}{Z_{\text{eff}}} | ||
| $$ | ||
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| $$ | ||
| \mathtt{abd} = 0.107 (1-0.35 \ \mathtt{alphan}+0.14 \ \mathtt{alphan}^2)(1-0.21 \ \mathtt{alphat})(1-0.2\times 10^{-3}\mathtt{ebeam}+0.09\times 10^{-6} \ \mathtt{ebeam}^2) | ||
| $$ | ||
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| $$ | ||
| \text{Current drive efficiency [A/W]} = \mathtt{abd} \times\frac{5}{R_0} \times0.1\frac{\mathtt{ten}}{n_{\text{e},20}} \times \frac{\mathtt{rjfunc}}{0.2}\mathtt{ffac} | ||
| $$ | ||
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| [^1]: N. A. Uckan and ITER Physics Group, *"ITER Physics Design Guidelines: 1989"*, ITER Documentation Series, No. 10, IAEA/ITER/DS/10 (1990) | ||
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