A methodology for decay heat characterization in molten salt reactors

Accurate decay heat prediction in molten salt reactors (MSRs) faces dual challenges: complex operational uncertainties and the need for interpretable models compatible with engineering workflows. This work presents a hybrid machine learning and segmented polynomial methodology that addresses both requirements through three key innovations. First, a modular data architecture encodes MSR-specific operational parameters (power density: 1-100 W cm -3 , humidity: 0-0.1 wt %, air ingress: 0-0.1 mol %) with uncertainty-aware temporal discretization spanning 15 orders of magnitude. Second, region-optimized machine learning models achieve 92.3 % root mean square error (RMSE) reduction over conventional polynomials while maintaining physical interpretability through automated piecewise equation generation. Third, dual front-end interfaces accelerate safety analyses — a Jupyter environment enables researchers to explore 10,000+ parameter combinations via interactive widgets, while a Streamlit web application reduces design iteration cycles through production-grade visualization tools. Operational deployment demonstrates prediction times of only a couple hundred milliseconds for 10 4 years decay profiles, enabling real-time optimization of spent fuel container designs. • A hybrid machine learning and segmented polynomial method for quantifying decay heat uncertainties in MSRs. • Data architecture encoding MSR-specific parameters, using uncertainty-aware temporal discretization. • Achieves a 92.3 % RMSE reduction over conventional polynomials, maintaining interpretability. • Dual interfaces: Jupyter environment and Streamlit app with interactive widgets and visualization tools.

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Publication Details

Journal
Nuclear Engineering and Design
Published
2025-10-22
DOI
https://doi.org/10.1016/j.nucengdes.2025.114524
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
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article

A methodology for decay heat characterization in molten salt reactors

Parikshit Bajpai, Rodrigo G.G. de Oliveira, Xingyue Yang, Elizabeth Parker-Quaife et al.
Nuclear Engineering and Design
Nuclear reactor physics and engineering
article

A methodology for decay heat characterization in molten salt reactors

Parikshit Bajpai, Rodrigo G.G. de Oliveira, Xingyue Yang, Elizabeth Parker-Quaife, Mauricio Tano, K. Otis
article en

Abstract

Accurate decay heat prediction in molten salt reactors (MSRs) faces dual challenges: complex operational uncertainties and the need for interpretable models compatible with engineering workflows. This work presents a hybrid machine learning and segmented polynomial methodology that addresses both requirements through three key innovations. First, a modular data architecture encodes MSR-specific operational parameters (power density: 1-100 W cm -3 , humidity: 0-0.1 wt %, air ingress: 0-0.1 mol %) with uncertainty-aware temporal discretization spanning 15 orders of magnitude. Second, region-optimized machine learning models achieve 92.3 % root mean square error (RMSE) reduction over conventional polynomials while maintaining physical interpretability through automated piecewise equation generation. Third, dual front-end interfaces accelerate safety analyses — a Jupyter environment enables researchers to explore 10,000+ parameter combinations via interactive widgets, while a Streamlit web application reduces design iteration cycles through production-grade visualization tools. Operational deployment demonstrates prediction times of only a couple hundred milliseconds for 10 4 years decay profiles, enabling real-time optimization of spent fuel container designs. • A hybrid machine learning and segmented polynomial method for quantifying decay heat uncertainties in MSRs. • Data architecture encoding MSR-specific parameters, using uncertainty-aware temporal discretization. • Achieves a 92.3 % RMSE reduction over conventional polynomials, maintaining interpretability. • Dual interfaces: Jupyter environment and Streamlit app with interactive widgets and visualization tools.

Nuclear Engineering and DesignVol. 446
Idaho National Laboratory (US)
Openalex Percentile: Top 59%
Nuclear reactor physics and engineering
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