Undergrad Education / Undergraduate Research Opportunity Program (UROP) / Comparative Neutronics Analysis for Tritium Breeding in the LIBRA Experiment
Nuclear fusion stands as a promising and sustainable energy source with the potential to revolutionize the global energy landscape. Among the numerous challenges facing fusion energy, the availability of tritium, a crucial fuel for fusion reactions, is a critical concern. Tritium breeding experiments aim to develop methods for producing tritium within the fusion reactor itself, ensuring a self- sustaining fusion process. This research proposal outlines a study that will apply advanced neutronics techniques to investigate and benchmark CAD-based and Constructive Solid Geometry (CSG) workflows in OpenMC for tritium breeding analysis within the context of the LIBRA Tritium Breeding Experiment.
UROP Description: Nuclear fusion stands as a promising and sustainable energy source with the potential to revolutionize the global energy landscape. Among the numerous challenges facing fusion energy, the availability of tritium, a crucial fuel for fusion reactions, is a critical concern. Tritium breeding experiments aim to develop methods for producing tritium within the fusion reactor itself, ensuring a self- sustaining fusion process. This research proposal outlines a study that will apply advanced neutronics techniques to investigate and benchmark CAD-based and Constructive Solid Geometry (CSG) workflows in OpenMC for tritium breeding analysis within the context of the LIBRA Tritium Breeding Experiment.
Objective
The primary objective of this research is to conduct a comprehensive neutronics analysis of the LIBRA Tritium Breeding Experiment, focusing on the bench-marking of CAD-based and CSG workflows against each other and against experimental results. Specifically, we aim to:
• Evaluate the tritium production and breeding performance within the experimental setup.
• Analyze neutron flux, energy spectra, and spatial distributions within the setup.
• Benchmark the CAD-based workflow against the CSG workflow and experimental data to assess their accuracy and performance.
• Provide valuable insights and recommendations for enhancing tritiu bmreeding efficiency in fusion reactors.
Prerequisites
Preferred but not mandatory prerequisites for this research include:
• Proficiency in Python for data analysis and scripting.
• Familiarity with version control systems, such as GitHub, for collaborative code development (preferred).
Literature Review
Tritium breeding in fusion reactors and the associated neutronics analysis techniques have been the subject of extensive research. The OpenMC code, a state-of-the-art Monte Carlo simulation tool for neutron transport, has played a pivotal role in nuclear reactor design and analysis. The investigation and bench- marking of CAD-based and CSG workflows in OpenMC, especially within the context of tritium breeding, is a relatively emerging area of research. This study aims to contribute to the evolving knowledge base in this field.
Expected Results
We anticipate the following outcomes:
• Evaluation of Tritium Production: Assessment of tritium production rates within the experimental setup.
• Neutron Flux Analysis: Analysis of neutron flux distribution, energy spec- tra, and spatial patterns.
• Workflow Benchmarking: Comparative evaluation of the CAD-based and CSG workflows against each other and experimental data, providing in- sights into their accuracy and performance.
• Material and Geometry Impact: Insights into how different materials and geometries affect tritium breeding efficiency.
These results will provide critical information to assess the feasibility and efficiency of tritium breeding in the experimental setup, while also shedding light on the best practices for utilizing advanced neutronics workflows in fusion reactor analysis.
References
1. Ferry, Sara E., et al. ”The LIBRA Experiment: Investigating Robust Tritium Accountancy in Molten FLiBe Exposed to a DT Fusion Neutron Spectrum.” Fusion Science and Technology 79.1 (2023): 13-35. 2. Romano, Paul K., et al. ”OpenMC: A state-of-the-art Monte Carlo code for research and development.” Annals of Nuclear Energy 82 (2015): 90- 97.
Head to MIT's UROP site to apply for this opportunity.