Documentation

Overview

OpenMC is an open-source Monte Carlo particle transport code for neutronics simulations. Our platform provides a streamlined interface to configure and run OpenMC simulations for lead-cooled fast reactor analysis.

Key Features

• Monte Carlo neutron transport with variance reduction
• ENDF/B-VIII.0 cross-section libraries
• k-eigenvalue calculations (k-eff)
• Flux, power, and reaction rate tallies
• Temperature-dependent cross sections (Doppler broadening)
• Depletion and burnup analysis

Overview

CFD-based thermohydraulic analysis using OpenFOAM for lead and LBE coolant flow simulations. Models heat transfer, temperature distributions, and natural circulation with liquid metal-specific correlations.

Key Features

• Lead/LBE-specific thermal properties
• Natural convection and forced circulation
• Conjugate heat transfer (fuel-clad-coolant)
• Temperature distribution mapping
• Pressure drop calculations

Overview

Iterative coupling between neutronic and thermohydraulic solvers to capture multi-physics feedback effects. Essential for accurate prediction of reactor behavior accounting for temperature feedback on cross-sections.

Feedback Effects

Overview

Comprehensive database of nuclear materials with validated physical and nuclear properties. All materials include temperature-dependent correlations where applicable and are compatible with ENDF/B-VIII.0 cross-section libraries.

Material Properties

Each material includes:

Example: Pure Lead Properties

{
  "id": "lead-pure",
  "name": "Pure Lead (Pb)",
  "category": "coolant",
  "composition": [
    { "isotope": "Pb-204", "weight_percent": 1.4 },
    { "isotope": "Pb-206", "weight_percent": 24.1 },
    { "isotope": "Pb-207", "weight_percent": 22.1 },
    { "isotope": "Pb-208", "weight_percent": 52.4 }
  ],
  "properties": {
    "density": "11441 - 1.2795*T [kg/m³]",
    "melting_point": 600.6,  // K
    "boiling_point": 2022,   // K
    "thermal_conductivity": "9.2 + 0.011*T [W/(m·K)]",
    "specific_heat": "175.1 - 0.0424*T + 1.43e-5*T² [J/(kg·K)]"
  },
  "temperature_range": { "min": 601, "max": 1800 }
}

Overview

ALFRED (Advanced Lead-cooled Fast Reactor European Demonstrator) is a 300 MWth pool-type lead-cooled fast reactor designed by the LEADER consortium.

Overview

MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is an accelerator-driven system (ADS) research reactor using lead-bismuth eutectic coolant, developed by SCK CEN in Belgium.

Overview

LFR-AS-200 is a 200 MWe small modular lead-cooled fast reactor designed for commercial deployment. Features passive safety systems and long refueling intervals.

Key Features

• Passive decay heat removal (DHRS)
• Natural circulation capable
• Seismic isolation
• Long-life core (10+ years without refueling)
• Modular construction

Overview

Create your own reactor configuration from scratch. Define custom geometry, materials, and operating conditions for research or design optimization studies.

Configuration Steps

Overview

OpenMC is the Monte Carlo particle transport code used for neutronic simulations. The platform runs OpenMC in containerized environments, but you can also run locally for development.

Docker Installation (Recommended)

The easiest way to run OpenMC locally:

# Pull the official OpenMC Docker image
docker pull openmc/openmc:latest

# Run with cross-section data
docker run -it -v $(pwd):/work openmc/openmc:latest

# Or use our pre-configured LFR image with all dependencies
docker pull lfrsim/openmc-lfr:latest

Cross-Section Libraries

Required nuclear data libraries:

# Download cross-section data
wget https://anl.box.com/shared/static/endfb-viii.0-hdf5.tar.gz
tar -xzf endfb-viii.0-hdf5.tar.gz

# Set environment variable
export OPENMC_CROSS_SECTIONS=/path/to/cross_sections.xml

Overview

OpenFOAM is used for CFD thermohydraulic simulations. We use a customized version with liquid metal correlations for lead and LBE coolants.

Docker Installation

# Pull OpenFOAM with liquid metal extensions
docker pull lfrsim/openfoam-lm:v2312

# Run interactive session
docker run -it -v $(pwd):/work lfrsim/openfoam-lm:v2312

# Inside container, source OpenFOAM
source /opt/openfoam/etc/bashrc

Native Installation (Ubuntu/Debian)

# Add OpenFOAM repository
curl -s https://dl.openfoam.com/add-debian-repo.sh | sudo bash

# Install OpenFOAM v2312
sudo apt-get update
sudo apt-get install openfoam2312

# Source environment
source /usr/lib/openfoam/openfoam2312/etc/bashrc

# Install LFR liquid metal extensions
git clone https://github.com/lfrsim/openfoam-lm-extensions.git
cd openfoam-lm-extensions && ./Allwmake

Installation

# Install from PyPI
pip install lfrsim

# Or install with optional dependencies
pip install lfrsim[all]  # Includes visualization tools

# For development
pip install lfrsim[dev]

Quick Start

from lfrsim import Client, Simulation

# Initialize client with API key
client = Client(api_key="your_api_key")

# Create a new simulation
sim = Simulation(
    name="ALFRED Analysis",
    template="alfred",
    simulation_type="neutronic"
)

# Configure parameters
sim.config.particles = 10_000_000
sim.config.batches = 500

# Submit and run
job = client.submit(sim)
print(f"Job ID: {job.id}")

# Wait for completion
result = job.wait()
print(f"k-eff: {result.keff} ± {result.keff_std}")

Working with Results

from lfrsim import Client
import matplotlib.pyplot as plt

client = Client(api_key="your_api_key")

# Get simulation results
result = client.get_result("sim_abc123")

# Access key metrics
print(f"k-eff: {result.keff}")
print(f"Peak power density: {result.peak_power_density} W/cm³")

# Get flux distribution as numpy array
flux = result.get_tally("flux")
print(f"Flux shape: {flux.shape}")

# Plot power map
power_map = result.get_power_map()
plt.imshow(power_map, cmap='hot')
plt.colorbar(label='Power (W)')
plt.savefig('power_distribution.png')

# Export to HDF5
result.export_hdf5("results.h5")

# Export to CSV
result.export_csv("results/")