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MOderated NEutron Target (MONET)

This simulation suite is designed to investigate neutron moderation target strategies for producing low-energy neutrons (<1 MeV) that can react with 171Tm through radiative capture at the National Ignition Facility (NIF).

Overview

The goal of this simulation suite is to determine whether it's possible to moderate a significant portion (>10%) of neutrons from DT fusion reactions to energies below 1 MeV for enhanced 171Tm capture reactions. The suite supports comprehensive parameter sweeps to optimize moderation efficiency.

Features

Geometry Options

The simulation suite supports multiple geometry options, including:

  • Standard NIF: DT fuel sphere + ablator shell + hohlraum
  • Double-shell: Two-shell implosion geometry
  • Coronal source: DT ice layer with laser entrance holes
  • Dual sources: Any combination of the above listed schemes on either side of a moderator
  • Dual filled hohlraum: Filled hohlraum with moderator and two coronal sources on either side

The user defines the geometry and sources in the pre-ignition state, which are then subsquently compressed with the user-defined convergence ratios.

Material Options

The simulation suite supports a wide range of material options, including: TODO: add materials options for each

  • Ablators:
  • Hohlraums:
  • Moderators:
  • Dopants:

Source Modeling

The simulation suite supports multiple source modeling options, including:

  • Muir energy distribution for DD and DT fusion neutrons
  • Delta function or Gaussian time dependence
  • Point or spherical source

Analysis Capabilities

The simulation suite supports comprehensive analysis capabilities, including:

  • 2D spatial flux/reaction maps
  • Energy and time spectra
  • Nuclear reaction tallies
  • Moderation efficiency calculations
  • Comprehensive parameter sweeps

Installation

To install the simulation suite, follow these steps:

  1. Clone the repository:
git clone <repository_url>
  1. Install dependencies:
pip install -r requirements.txt
  1. Ensure OpenMC is properly configured with nuclear data libraries.

Quick Start

Single Simulation

To run a single NIF simulation, use the following command:

python scripts/run_single.py

Parameter Sweep

To run a parameter sweep, use the following command:

python scripts/run_sweep.py

Usage Examples

Basic Simulation

To set up and run a basic simulation, use the following code:

Parameter Sweep

To run a parameter sweep, use the following code:

Data Management

Results are automatically organized with: TODO: add data organization

  • Simulation parameters
  • Tally data
  • Plots
  • Summary statistics
  • Parameter sweep databases

Customization

Adding New Materials

To add a new material

Adding New Geometries

To add a new geometry

Custom Analysis

To add custom analysis

Contributing

Contributions are welcome! To contribute to the project, please follow these steps:

  1. Create a new branch for your feature or bug fix
  2. Make your changes and commit them
  3. Push your changes to your forked repository
  4. Submit a pull request

License

This project is licensed under the MIT License - see the LICENSE file for details.

Acknowledgements

This project was made possible through funding from

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