d0fus 2.0.1

Design 0-dimensional for Fusion Systems - Tokamak power plant design and optimization tool

D0FUS

D0FUS (Design 0-dimensional for Fusion Systems) is a Python tokamak systems code for fast 0D/1D design-space exploration, covering plasma physics, superconducting magnet engineering, and techno-economic assessment. It is developed at CEA-IRFM.

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Installation

Three installation options are available. Option A is recommended for most users (no prior Python knowledge required).

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Option A: Spyder standalone (recommended)

This is the simplest path. Spyder comes with its own bundled Python, with no separate Python installation needed.

Step 1: Download and install Spyder

Go to spyder-ide.org and download the installer for your operating system (Windows, macOS, or Linux). Run the installer and follow the on-screen instructions. Default settings are fine.

Step 2: Download D0FUS

If you have git installed, open a terminal (macOS/Linux) or Command Prompt (Windows) and run:

git clone https://github.com/IRFM/D0FUS.git

Otherwise, go to github.com/IRFM/D0FUS, click Code → Download ZIP, and extract the archive somewhere on your computer (e.g. C:\Users\you\D0FUS\ on Windows or ~/D0FUS/ on macOS/Linux).

Step 3: Open Spyder

Launch Spyder from your applications menu (or desktop shortcut). You should see a layout with a code editor on the left, a file explorer on the top right, and an IPython console on the bottom right.

Step 4: Open D0FUS.py in Spyder

Go to File → Open… and open D0FUS.py from the D0FUS/ folder. Spyder will automatically set the working directory to D0FUS/. You can confirm this by checking the folder path displayed in the toolbar at the top.

Step 5: Install dependencies

In the IPython console (bottom-right panel), type the following and press Enter:

%pip install -r requirements.txt

The %pip magic command installs packages directly into Spyder's internal Python. Since the Spyder standalone bundles its own pip, no prior installation is needed. Since the working directory is already set to D0FUS/, no path specification is needed. Wait for all packages to finish installing.

If %pip fails, try: !pip install -r requirements.txt. If pip itself is missing (unlikely with the standalone), reinstalling Spyder usually fixes it.

Step 6: Run D0FUS

Press F5 (or click the green ▶ Run file button). A file-picker dialog will appear. Navigate to D0FUS_INPUTS/ and select 1_run_ITER.txt. D0FUS will run and print results to the IPython console. Figures will open automatically.

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Option B: Miniforge (for advanced users)

Miniforge is a free, community-maintained conda distribution with no commercial restrictions. Recommended if you manage multiple Python projects.

Install Miniforge, then open a Miniforge Prompt (Windows) or terminal (macOS/Linux):

conda create -n d0fus python=3.11
conda activate d0fus
conda install pip
conda install spyder
git clone https://github.com/IRFM/D0FUS.git
cd D0FUS
pip install -r requirements.txt
spyder

Once Spyder is open, follow Steps 5–6 from Option A. Alternatively, run directly from the terminal:

python D0FUS.py
# When prompted, enter the path to the input file:
# D0FUS_INPUTS/1_run_ITER.txt

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Option C: pip install (headless / script integration)

For use without a GUI, or to import D0FUS as a library in your own scripts:

pip install d0fus

To run the ITER example case from a script:

from D0FUS_EXE import D0FUS_run

results = D0FUS_run.run("D0FUS_INPUTS/1_run_ITER.txt")
print(f"Q = {results['Q']:.1f},  COE = {results['COE']:.0f} EUR/MWh")

Note: input files (D0FUS_INPUTS/) are not included in the PyPI package. Clone the repository separately to access them.

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Project Structure

D0FUS/
├── D0FUS_BIB/                          # Core library modules
│   ├── D0FUS_import.py                     # Centralised imports
│   ├── D0FUS_parameterization.py           # Physical constants, GlobalConfig dataclass
│   ├── D0FUS_physical_functions.py         # Plasma physics (profiles, bootstrap, q, RE…)
│   ├── D0FUS_radial_build_functions.py     # Engineering (TF/CS/CICC/quench)
│   ├── D0FUS_cost_functions.py             # Techno-economic models (Sheffield, Whyte)
│   ├── D0FUS_cost_data.py                  # Reference cost data and currency conversions
│   └── D0FUS_figures.py                    # Full figure catalogue (27+ figures)
│
├── D0FUS_INPUTS/                       # Input parameter files
│   ├── 1_run_ITER.txt                      # ITER Q=10 reference case (RUN mode)
│   ├── 2_scan_ITER.txt                     # 2D scan around ITER point (SCAN mode)
│   └── 3_genetic_ITER.txt                  # Genetic optimisation around ITER (OPTIMIZATION mode)
│
├── D0FUS_OUTPUTS/                      # Generated outputs (auto-created)
│   ├── Run_D0FUS_YYYYMMDD_HHMMSS/         # Single run results + figures
│   ├── Scan_D0FUS_YYYYMMDD_HHMMSS/        # 2D scan maps
│   └── Genetic_D0FUS_YYYYMMDD_HHMMSS/     # Optimisation results
│
├── D0FUS_EXE/                          # Execution modules
│   ├── D0FUS_run.py                        # Single design point
│   ├── D0FUS_scan.py                       # 2D parameter scan
│   └── D0FUS_genetic.py                    # Genetic algorithm optimisation
│
├── D0FUS.py                            # Main entry point
├── requirements.txt
└── README.md

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Execution Modes

D0FUS detects the execution mode from the input file format:

Mode	Purpose	Input format	Parameters
RUN	Single design point	R0 = 9	Fixed values only
SCAN	2D parameter space	R0 = [3, 9, 25]	Exactly 2 parameters with [min, max, n_points]
OPTIMIZATION	Genetic algorithm cost minimisation	R0 = [3, 9]	2+ parameters with [min, max]

RUN mode evaluates a single tokamak configuration and outputs all plasma parameters, magnetic fields, power balance, radial build, cost of electricity, and RE indicators.

SCAN mode generates 2D maps over two parameters, visualising feasibility regions bounded by stability limits (Greenwald, Troyon, kink) and engineering constraints. Iso-contours of any output quantity registered in OUTPUT_REGISTRY can be overlaid.

OPTIMIZATION mode uses a DEAP genetic algorithm to find the configuration minimising cost (COE by default) while satisfying all physics and engineering constraints. The budget ceiling C_invest_max is enforced via an exponential penalty.

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Input

Parameter Handling

All parameters have physically motivated default values (DEMO-class baseline). When an input file is provided, only the specified parameters are overwritten. This allows minimal input files:

R0 = 7
Bmax_TF = 14
Supra_choice = REBCO

Parameter Reference

Geometry

Parameter	Description	Unit	Default
P_fus	Fusion power	MW	2000
R0	Major radius	m	9.0
a	Minor radius	m	3.0
b	Blanket + shield radial thickness	m	1.2
Option_Kappa	Elongation model	—	Wenninger
κ_manual	Manual elongation (if Option_Kappa = Manual)	—	1.9

Options for Option_Kappa: Wenninger, Stambaugh, Freidberg, Manual.

Magnetic Field

Parameter	Description	Unit	Default
Bmax_TF	Peak field on TF conductor	T	12.0
Bmax_CS_adm	Admissible peak field on CS	T	25.0

Technology

Parameter	Description	Unit	Default	Options
Supra_choice	Superconductor material	—	Nb3Sn	NbTi, Nb3Sn, REBCO
Radial_build_model	Stress model	—	D0FUS	academic, D0FUS, CIRCE
Choice_Buck_Wedg	TF mechanical configuration	—	Wedging	Plug, Bucking, Wedging
Chosen_Steel	Structural steel grade	—	316L	316L, N50H, JK2LB, Manual

Plasma Physics

Parameter	Description	Unit	Default	Options
Scaling_Law	Energy confinement scaling law	—	IPB98(y,2)	IPB98(y,2), ITPA20, ITPA20-IL, DS03, L-mode, ITER89-P
H	Confinement enhancement factor	—	1.0
Tbar	Volume-averaged ion temperature	keV	14.0
Plasma_profiles	Profile peaking preset	—	H	L, H, Advanced, Manual
nu_n_manual	Density peaking factor (Manual only)	—	0.1
nu_T_manual	Temperature peaking factor (Manual only)	—	1.0
rho_ped	Normalised pedestal radius	—	1.0
n_ped_frac	Pedestal density fraction n_ped/n̄	—	0.0
T_ped_frac	Pedestal temperature fraction T_ped/T̄	—	0.0
Bootstrap_choice	Bootstrap current model	—	Redl	Freidberg, Segal, Sauter, Redl
Option_q95	q₉₅ formula	—	Sauter	Sauter, ITER_1989
L_H_Scaling_choice	L-H threshold scaling	—	New_Ip	Martin, New_S, New_Ip
Plasma_geometry	Volume integral geometry	—	Academic	Academic, D0FUS
Zeff	Effective plasma charge	—	2.0
impurity_species	Impurity species (radiation)	—	''	W, Ar, Ne, C, N, Kr
f_imp_core	Impurity concentration n_imp/n_e	—	''
rho_rad_core	Core/edge radiation boundary	—	0.75

Operation

Parameter	Description	Unit	Default	Options
Operation_mode	Operating scenario	—	Pulsed	Steady-State, Pulsed
Temps_Plateau_input*	Flat-top burn duration	s	3600
P_aux_input*	Auxiliary heating power	MW	50
CD_source	Current drive model	—	Academic	Academic (recommended), LHCD, ECCD, NBCD, Multi (dev.)
gamma_CD_acad	CD figure of merit (Academic mode)	MA/(MW·m²)	0.20
eta_WP_acad	Wall-plug efficiency (Academic mode)	—	0.40

*Only relevant when Operation_mode = Pulsed.

Note on CD models: only CD_source = Academic is fully validated. Technology-specific models (LHCD, ECCD, NBCD, Multi) are under active development and should not be used for production runs.

Disruption / Runaway Electron Indicators

These parameters control the post-convergence RE indicator computation. They do not enter the main physics solver.

Parameter	Description	Unit	Default
tau_TQ	Thermal quench e-folding time	s	1e-3
Te_final_eV	Post-TQ residual electron temperature	eV	5.0
pellet_dilution	Density multiplication from SPI/MGI	—	10.0

Techno-Economic Model

Parameter	Description	Unit	Default
cost_model	Cost model	—	Sheffield
discount_rate	Real discount rate	—	0.07
T_life	Plant operational lifetime	yr	40
T_build	Construction duration	yr	10
contingency	Contingency fraction	—	0.15
Util_factor	Utilisation factor	—	0.85
Supra_cost_factor	SC coil cost multiplier vs Cu	—	2.0
C_invest_max	Capital cost ceiling (genetic)	M EUR	25 000

Set cost_model = None to skip cost computation entirely.

Input File Format

RUN mode: fixed values only:

R0 = 9
Bmax_TF = 13
Supra_choice = Nb3Sn

See D0FUS_INPUTS/1_run_ITER.txt for a complete example.

SCAN mode: exactly 2 scan parameters with [min, max, n_points]:

R0 = [3, 9, 25]
a  = [1, 3, 25]

See D0FUS_INPUTS/2_scan_ITER.txt for a complete example.

OPTIMIZATION mode: 2+ parameters with [min, max]:

R0     = [3, 9]
a      = [1, 3]
Bmax_TF = [10, 16]
fitness_objective = COE
C_invest_max = 20000

See D0FUS_INPUTS/3_genetic_ITER.txt for a complete example.

Genetic Algorithm Settings

Parameter	Description	Default
population_size	Individuals per generation	50
generations	Maximum generations	100
crossover_rate	Crossover probability	0.7
mutation_rate	Mutation probability	0.2
fitness_objective	Quantity to minimise	COE

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Output

RUN Mode Output

D0FUS_OUTPUTS/Run_D0FUS_YYYYMMDD_HHMMSS/
├── input_parameters.txt        # Copy of input configuration
├── output_results.txt          # Complete calculation results
└── figures/                    # 10 run-specific PNG figures (150 dpi)
    ├── 01_cross_section.png
    ├── 02_miller_surfaces.png
    ├── 03_shaping_profiles.png
    ├── 04_kinetic_profiles.png
    ├── 05_q_profile.png
    ├── 06_radiation_profile.png
    ├── 07_TF_side_view.png
    ├── 08_CICC_TF.png
    ├── 09_CS_cross_section.png
    └── 10_CICC_CS.png

Output quantities include:

• Plasma parameters: Ip, n̄_e, T̄, β_N, Q, τ_E, q₉₅, f_bs
• Magnetic fields: B0, B_CS, B_pol
• Power balance: P_fus, P_CD, P_rad, P_sep, P_elec
• Radial build: TF coil thickness, CS inner/outer radius, first-wall area
• Current profile: j_Ohm(ρ), j_CD(ρ), j_bs(ρ), q(ρ) (self-consistent iteration)
• Techno-economics: COE [EUR/MWh], C_invest [M EUR]
• RE indicators: I_RE_seed, I_RE_aval, f_RE/Ip, E_RE_kin

SCAN Mode Output

D0FUS_OUTPUTS/Scan_D0FUS_YYYYMMDD_HHMMSS/
├── scan_parameters.txt
└── scan_map_[iso]_[bg].png     # 2D map (300 dpi)

Available scan output quantities (OUTPUT_REGISTRY):

Category	Quantities
Performance	Q, P_fus, P_elec, COE, C_invest
Plasma	Ip, n̄, β_N, β_T, q₉₅, τ_E, f_bs, f_Greenwald
Fields	B0, B_CS, B_pol
Power	P_rad, P_sep, P_CD, P_Ohm
Engineering	d_TF, d_CS, S_FW
RE indicators	I_RE_seed, I_RE_aval, f_RE_Ip, f_RE_avg, f_RE_core, E_RE_kin

OPTIMIZATION Mode Output

D0FUS_OUTPUTS/Genetic_D0FUS_YYYYMMDD_HHMMSS/
├── optimization_config.txt     # Bounds, algorithm settings
├── optimization_results.txt    # Best solution, COE, C_invest
└── convergence_plot.png        # Fitness evolution over generations

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Figures Catalogue

plot_run() generates 10 run-specific figures. plot_all() generates the full 27-figure catalogue, including:

Group	Figures
Geometry & shaping	κ scaling, LCFS comparison, Miller flux surfaces, κ(ρ)/δ(ρ) profiles
Kinetics	n(ρ), T(ρ), p(ρ) profiles; line- vs volume-averaged density
Radiation	Lz(T) cooling functions, P_rad(ρ) profile, helium-ash fraction
Current & q	q(ρ) with j_Ohm/j_CD/j_bs decomposition
Magnets	Jc(B,T) scaling (NbTi/Nb₃Sn/REBCO), TF thickness vs B_max, CS thickness vs flux swing
Engineering drawings	Princeton-D TF side view, CS cross-section, CICC cross-section (hex-packed strands)
Benchmarks	TF coil benchmark table, CS benchmark table, CIRCE0D stress validation

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Physics Models

Plasma Geometry

D0FUS supports two plasma geometry models, selected via Plasma_geometry:

Model	Description	When to use
Academic	Cylindrical-torus approximation, uniform κ and δ	Large parameter scans, fast runs
D0FUS	Full Miller flux-surface parameterisation (Miller et al. 1998) with PCHIP κ(ρ) and δ(ρ) profiles	Single-point analysis, triangularity effects (δ > 0.3)

The Miller model computes V′(ρ) numerically from the Jacobian of the (R, Z) flux-surface coordinates, with κ(0) = 1 and δ(0) = 0 enforced on-axis (Ball & Parra 2015). Volume integrals (P_fus, ⟨nT⟩, W_th, P_rad, bootstrap current) are weighted by V′(ρ)/V when in D0FUS mode.

Safety Factor Profile

Two q(ρ) models are available:

• Analytical (f_q_profile): parameterised as j(ρ) ∝ (1 − ρ²)^α_J, with α_J derived automatically from the resistive diffusion timescale τ_R.
• Self-consistent (f_q_profile_selfconsistent): Picard iteration on j_total(ρ) = j_Ohm(ρ) + j_CD(ρ) + j_bs(ρ). Produces a decomposed current profile visualisation.

The q₉₅ boundary value is computed via the Option_q95 selector:

Option	Formula	Shaping argument
Sauter	Sauter, Fusion Eng. Des. 112 (2016), Eq. 30	LCFS values (κ_edge, δ_edge)
ITER_1989	ITER Physics Design Guidelines, Uckan (1990)	ψ_N = 0.95 surface values (κ₉₅, δ₉₅)

Bootstrap Current

Four models are supported via Bootstrap_choice:

Model	Reference	Recommended use
Freidberg	Freidberg (2007)	Quick estimates
Segal	Segal (1993)	Alternative analytical
Sauter	Sauter et al., PoP 6 (1999)	Full neoclassical, all collisionality regimes
Redl	Redl et al., PoP 28 (2021)	Default, improved high-ν* accuracy

Confinement Scaling Laws

Scaling_Law options: IPB98(y,2), ITPA20, ITPA20-IL, DS03, L-mode, L-mode OK, ITER89-P.

Impurity Radiation

Line radiation from seeded or intrinsic impurities is modelled via the Mavrin (2018) cooling function tabulation (validated against ADAS). Supported species: W, Ar, Ne, C, N, Kr. Core radiation (ρ < rho_rad_core) is subtracted from the power balance; edge radiation reduces the divertor load P_sep.

Runaway Electron Diagnostic

Post-convergence RE indicators are computed by compute_RE_indicators() using:

• Hot-tail seed: Smith & Verwichte (2008), exponentially sensitive to τ_TQ
• Avalanche amplification: Breizman et al. (2019)
• Coulomb logarithm: single relativistic lnΛ ≈ 15.3 via _coulomb_log_relativistic()
• Literature benchmarks: Martín-Solís et al. (2017)

Outputs include I_RE_seed, I_RE_aval, f_RE/Ip, and kinetic energy E_RE_kin. These are indicators for comparative design ranking, not quantitative predictions. Configurable via tau_TQ, Te_final_eV, and pellet_dilution.

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Engineering Models

Radial Build

The TF coil inboard leg is shaped as a Princeton-D contour (Gralnick & Tenney 1976). Conductor sizing follows a three-level helium fraction hierarchy distinguishing the cooling pipe (f_He_pipe), interstitial void (f_void, LTS only), and active SC fraction. Three structural models are available via Radial_build_model: a simplified analytical model (academic), the D0FUS stress model (D0FUS), and the multi-layer CIRCE0D solver (CIRCE).

Superconductor

Critical current density scaling laws are implemented for NbTi, Nb₃Sn (ITER strand parameterisation), and REBCO (Senatore 2024 / Fujikura 2019 datasets). Quench protection is sized via the Maddock hot-spot criterion, with dump time computed from stored magnetic energy and conductor current.

Techno-Economic Model

Capital investment and COE are computed using the Sheffield & Milora (2016) volume-based cost scaling (2010 USD, converted to 2025 EUR). Component costs cover the SC coil set, blanket, shield, auxiliary heating, heat transfer system, balance of plant, buildings, and annual O&M. A simplified surface-proportional model (Whyte 2024) is also available for cross-checks.

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Benchmarks and Validation

The primary benchmark case is ITER Q=10 (Ip = 15 MA, B0 = 5.3 T, R0 = 6.2 m, P_fus = 500 MW), provided as D0FUS_INPUTS/1_run_ITER.txt. The main plasma and engineering quantities are recovered to the correct order of magnitude; detailed quantitative agreement is still being refined.

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Contributing

Contributions are welcome. Please contact:

• Email: [e-mail]

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License

This project is licensed under the CeCILL-C License, a French free software license compatible with the GNU LGPL.

See the LICENSE file for details.

© 2025 CEA/IRFM

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