Abstract
This manuscript proposes a novel information-theoretic approach to the quantification of experimental relevance, i.e., coverage, to achieve optimal data assimilation results for nuclear engineering applications. Specifically, this work posits the need for a new metric, called coverage ((Formula presented.)) of an application’s quantity of interest, i.e., eigenvalue or power peaking for an advanced reactor concept, defined herein as the theoretically maximum achievable reduction in the quantity’s uncertainty given measurements from a pool of experiments in a manner that is independent of the data assimilation procedure employed. Currently, reduction in a quantity’s uncertainty is strongly biased by the underlying assumptions of the assimilation procedure to account for the under-determined nature of such problems and the similarity criterion employed to identify relevant experiments. To address this challenge, this work has developed a coverage metric, (Formula presented.), based on mutual information, which establishes a new conceptual framework for assessing coverage, one that is independent of the model parameters and responses degree of variations in both the experimental and application domains, i.e., linear vs non-linear, and their prior uncertainty distributions, i.e., Gaussian vs. non-Gaussian. The (Formula presented.) is an entropic measure capable of addressing coverage for general nonlinear problems with non-Gaussian uncertainties and inclusive of the measurement uncertainties from multiple experiments. Numerical experiments from manufactured analytical problems as well as a set of benchmarks from the ICSBEP handbook are employed to demonstrate its theoretical and practical performance as compared to the (Formula presented.) -based experiment selection methodology, commonly employed in the neutronic community. The manuscript then employs other well-known adaptations to existing data assimilation methodologies for nonlinear and non-Gaussian problems capable of achieving the coverage posited by (Formula presented.).
| Original language | English |
|---|---|
| Article number | 1675308 |
| Journal | Frontiers in Nuclear Engineering |
| Volume | 4 |
| DOIs | |
| State | Published - 2025 |
Funding
The author(s) declare that financial support was received for the research and/or publication of this article. This work was supported in part by the U.S. Department of Energy’s (DOE) National Nuclear Security Administration, Office of Defense Nuclear Nonproliferation Research and Development (NA-22). The authors also acknowledge the DOE/NRC Collaboration for Criticality Safety Support for Commercial-Scale HALEU for Fuel Cycles and Transportation (DNCSH) initiative for their support and collaboration.
Keywords
- Bayesian data assimilation
- criticality safety
- experimental coverage
- nuclear criticality analysis
- similarity analysis
- uncertainty quantification