Abstract
Microreactors represent a transformative advancement in nuclear energy, offering compact, flexible, and transportable power generation for remote locations, industrial applications, and national security needs. Their unique configurations, including Tristructural Isotropic (TRISO) fuel, alternative cooling methods such as heat pipes, and innovative control mechanisms, require specialized simulation tools that extend beyond traditional reactor analysis frameworks. This work presents a novel multiphysics modeling approach integrating Monte Carlo neutron transport with detailed thermal solvers to enhance predictive capabilities for microreactor design and safety assessment. The developed simulation framework couples the Shift Monte Carlo neutron transport code with the pyMP platform, enabling the accurate representation of steady-state and transient reactor behavior. pyMP incorporates a flexible shift driver package for interfacing with Shift, a thermal package containing conduction and convective cooling solvers, and a multiphysics package responsible for integrating all physics domains. Two representative microreactor models were analyzed: a gas-cooled TRISO-fueled design with control rods (Core A) and a heat pipe-cooled design with rotating control drums (Core B). Results from power ramp and control drum search studies demonstrate the framework’s capability to model reactivity feedback, heat transfer, and control mechanisms with high fidelity. These developments mark a significant step toward comprehensive, high-accuracy microreactor simulation, supporting design optimization and regulatory assessment.
| Original language | English |
|---|---|
| Title of host publication | Proceedings of Advances in Nuclear Fuel Management, ANFM 2025 |
| Publisher | American Nuclear Society |
| Pages | 710-720 |
| Number of pages | 11 |
| ISBN (Electronic) | 9780894482267 |
| DOIs | |
| State | Published - 2025 |
| Externally published | Yes |
| Event | 2025 Advances in Nuclear Fuel Management, ANFM 2025 - Clearwater Beach, United States Duration: Jul 20 2025 → Jul 23 2025 |
Publication series
| Name | Proceedings of Advances in Nuclear Fuel Management, ANFM 2025 |
|---|
Conference
| Conference | 2025 Advances in Nuclear Fuel Management, ANFM 2025 |
|---|---|
| Country/Territory | United States |
| City | Clearwater Beach |
| Period | 07/20/25 → 07/23/25 |
Funding
The authors would like to express their gratitude to the Shift development team for assistance in installing and running Shift on HPC platforms during this development effort, and for their responsiveness to issues identified during usage of the code. This material is based upon work supported by the U.S. Department of Energy Small Business Innovative Research program under Award Number DE-FOA-0003110. Calculations were performed on the Sawtooth high-performance computer at INL which is supported for the VERA Users Group (https://vera.ornl.gov) by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Keywords
- microreactors
- multiphysics
- simulation
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