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Merge branch 'main' into 3344-implement-suite-of-new-bootstrap-curren…
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chris-ashe committed Nov 8, 2024
2 parents 9baa160 + 42780a9 commit 2cc0bc9
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8 changes: 4 additions & 4 deletions documentation/proc-pages/development/add-vars.md
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Expand Up @@ -247,15 +247,15 @@ Constraint equations are added to *PROCESS* in the following way:
!! Logic change during pre-factoring: err, symbol, units will be assigned only if present.
!! ffuspow : input real : f-value for maximum fusion power
!! powfmax : input real : maximum fusion power (MW)
!! powfmw : input real : fusion power (MW)
!! fusion_power : input real : fusion power (MW)
use constraint_variables, only: ffuspow, powfmax
use physics_variables, only: powfmw
use physics_variables, only: fusion_power
implicit none
type (constraint_args_type), intent(out) :: args
args%cc = 1.0D0 - ffuspow * powfmax/powfmw
args%cc = 1.0D0 - ffuspow * powfmax/fusion_power
args%con = powfmax * (1.0D0 - args%cc)
args%err = powfmw * args%cc
args%err = fusion_power * args%cc
args%symbol = '<'
args%units = 'MW'
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10 changes: 5 additions & 5 deletions documentation/proc-pages/development/standards.md
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Expand Up @@ -259,7 +259,7 @@ real(kind(1.0D0)) :: alphan = 0.25D0
real(kind(1.0D0)) :: alphap = 0.0D0
!! Pressure profile index
real(kind(1.0D0)) :: alpharate = 0.0D0
real(kind(1.0D0)) :: alpha_rate_density = 0.0D0
!! Alpha particle production rate (particles/m3/sec)
```

Expand Down Expand Up @@ -306,16 +306,16 @@ subroutine constraint_eqn_001(args)
!! - \( T_i \) -- density weighted average ion temperature [keV]
!! - \( B_{tot} \) -- total toroidal + poloidal field [T]
use physics_variables, only: betaft, betanb, dene, ten, dnitot, tin, btot, beta
use constants, only: echarge,rmu0
use physics_variables, only: betaft, beta_beam, dene, ten, dnitot, tin, btot, beta
use constants, only: electron_charge,rmu0
implicit none
type(constraint_args_type), intent(out) :: args
!! constraint derived type
args%cc = 1.0D0 - (betaft + betanb + &
2.0D3*rmu0*echarge * (dene*ten + dnitot*tin)/btot**2 )/beta
args%cc = 1.0D0 - (betaft + beta_beam + &
2.0D3*rmu0*electron_charge * (dene*ten + dnitot*tin)/btot**2 )/beta
args%con = beta * (1.0D0 - args%cc)
args%err = beta * args%cc
args%symbol = '='
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Expand Up @@ -49,11 +49,11 @@ $$
Deuterium and tritium beam densities

$$
\mathtt{dend} = n_{\text{ion}} \times (1-\mathtt{ftritbm})
\mathtt{dend} = n_{\text{ion}} \times (1-\mathtt{f_tritium_beam})
$$

$$
\mathtt{dent} = n_{\text{ion}} \times \mathtt{ftritbm}
\mathtt{dent} = n_{\text{ion}} \times \mathtt{f_tritium_beam}
$$

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 $\mathtt{fpion}$
Expand All @@ -72,7 +72,7 @@ plus correction terms outlined in Culham Report AEA FUS 172.
| $\mathtt{aspect}$, $A$ | 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 $(\text{keV})$ |
| $\mathtt{beam_energy}$ | 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 $(\text{m})$ |
Expand Down Expand Up @@ -114,7 +114,7 @@ $$
Beam energy in MeV

$$
\mathtt{ebmev} = \frac{\mathtt{enbeam}}{10^3}
\mathtt{ebmev} = \frac{\mathtt{beam_energy}}{10^3}
$$

x and y coefficients of function J0(x,y) (IPDG89)
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Expand Up @@ -39,11 +39,11 @@ $$

Deuterium and tritium beam densities:
$$
n_D = n_i * (1.0 - \mathtt{ftritbm})
n_D = n_i * (1.0 - \mathtt{f_tritium_beam})
$$

$$
n_T = n_i * \mathtt{ftritbm}
n_T = n_i * \mathtt{f_tritium_beam}
$$

Power split to ions / electrons is calculated via the the `cfnbi` method described [here](nbi_overview.md)
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Expand Up @@ -33,7 +33,7 @@ The answer ECGAM is the normalised efficiency $n_{\text{e}}IR/P$ with $n_{\text{


$$
\mathtt{mcsq} = 9.1095\times10^{-31} \frac{c^2}{1 \text{keV}}
\mathtt{mcsq} = m_{\text{e}} \frac{c^2}{1 \text{keV}}
$$

$$
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Expand Up @@ -11,7 +11,7 @@ turbines. Figure 1 shows the power flow.

## Divertor

All of the charged particle transport power leaving the plasma (excluding the `1-falpha` portion of
All of the charged particle transport power leaving the plasma (excluding the `1-f_alpha_plasma` portion of
the alpha power that escapes directly to the first wall) is assumed to be absorbed in the divertor,
along with a proportion `fdiv` of the radiation power and the neutron power.

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26 changes: 13 additions & 13 deletions documentation/proc-pages/physics-models/error.txt
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Expand Up @@ -207,7 +207,7 @@ deuterium-tritium reaction:
\]

20\% of the energy produced is given to the alpha particles (\(^4\)He),
a fraction of which remain (c.f. \texttt{falpha}) within the plasma and
a fraction of which remain (c.f. \texttt{f_alpha_plasma}) within the plasma and
thermalise (slow down) due to collisions, thus heating the plasma. The
remaining 80\% is carried away by the neutrons, which deposit their
energy within the blanket and shield.
Expand Down Expand Up @@ -254,17 +254,17 @@ integrated over the plasma profiles (correctly, with or without
pedestals).

The fractional composition of the `fuel' ions (D, T and \(^3\)He) is
controlled using the three variables \texttt{fdeut}, \texttt{ftrit} and
\texttt{fhe3}, respectively:
controlled using the three variables \texttt{f_deuterium}, \texttt{f_tritium} and
\texttt{f_helium3}, respectively:

\[\begin{aligned}
n_{\mbox{fuel}} & = n_D + n_T + n_{\mathrm{^{3}He}} \;\;\; \mbox{particles/m$^3$} \\
n_D & = \mathtt{fdeut} \, n_{\mbox{fuel}} \\
n_T & = \mathtt{ftrit} \, n_{\mbox{fuel}} \\
n_{\mathrm{^{3}He}} & = \mathtt{fhe3} \, n_{\mbox{fuel}}
n_D & = \mathtt{f_deuterium} \, n_{\mbox{fuel}} \\
n_T & = \mathtt{f_tritium} \, n_{\mbox{fuel}} \\
n_{\mathrm{^{3}He}} & = \mathtt{f_helium3} \, n_{\mbox{fuel}}
\end{aligned}\]

PROCESS checks that \(fdeut + ftrit + fhe3 = 1.0\), and stops with an
PROCESS checks that \(f_deuterium + f_tritium + f_helium3 = 1.0\), and stops with an
error message otherwise.

\subsection{Plasma Profiles}\label{plasma-profiles}
Expand Down Expand Up @@ -499,8 +499,8 @@ model. The available impurities are as follows:
As stated above, the number density fractions for hydrogen (all
isotopes) and helium need not be set, as they are calculated by the code
to ensure that plasma quasi-neutrality is maintained, and taking into
account the fuel ratios \texttt{fdeut}, \texttt{ftrit} and
\texttt{fhe3}, and the alpha particle fraction \texttt{ralpne} which may
account the fuel ratios \texttt{f_deuterium}, \texttt{f_tritium} and
\texttt{f_helium3}, and the alpha particle fraction \texttt{ralpne} which may
be input by the user.

The impurity fraction of one of the elements listed in array
Expand Down Expand Up @@ -994,18 +994,18 @@ is derived directly from the energy confinement scaling law.
\texttt{iradloss\ =\ 0} -- Total power lost is scaling power plus
radiation

\texttt{pscaling\ +\ pradpv\ =\ falpha*palppv\ +\ pchargepv\ +\ pohmpv\ +\ pinjmw/vol}
\texttt{pscaling\ +\ pradpv\ =\ f_alpha_plasma*alpha_power_density\ +\ charged_power_density\ +\ pohmpv\ +\ pinjmw/plasma_volume}

\texttt{iradloss\ =\ 1} -- Total power lost is scaling power plus core
radiation only

\texttt{pscaling\ +\ pcoreradpv\ =\ falpha*palppv\ +\ pchargepv\ +\ pohmpv\ +\ pinjmw/vol}
\texttt{pscaling\ +\ pcoreradpv\ =\ f_alpha_plasma*alpha_power_density\ +\ charged_power_density\ +\ pohmpv\ +\ pinjmw/plasma_volume}

\texttt{iradloss\ =\ 2} -- Total power lost is scaling power only, with
no additional allowance for radiation. This is not recommended for power
plant models.

\texttt{pscaling\ =\ falpha*palppv\ +\ pchargepv\ +\ pohmpv\ +\ pinjmw/vol}
\texttt{pscaling\ =\ f_alpha_plasma*alpha_power_density\ +\ charged_power_density\ +\ pohmpv\ +\ pinjmw/plasma_volume}

\subsection{Plasma Core Power Balance}\label{plasma-core-power-balance}

Expand All @@ -1027,7 +1027,7 @@ The primary sources of power are the fusion reactions themselves, ohmic
power due to resistive heating within the plasma, and any auxiliary
power provided for heating and current drive. The power carried by the
fusion-generated neutrons is lost from the plasma, but is deposited in
the surrounding material. A fraction \texttt{falpha} of the alpha
the surrounding material. A fraction \texttt{f_alpha_plasma} of the alpha
particle power is assumed to stay within the plasma core to contribute
to the plasma power balance. The sum of this core alpha power, any power
carried by non-alpha charged particles, the ohmic power and any injected
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