Full Spectrum LOCA Analysis Using BEPU Monte Carlo
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Solution Overview
Problem
Current safety analysis methods for nuclear reactors primarily focus on small and large break Loss of Coolant Accidents (LOCAs) and neglect intermediate breaks, which are not thoroughly analyzed due to simplistic engineering arguments, limiting the comprehensive assessment of reactor safety.
Innovation Solution
A computational system and method that applies the Best-Estimate Plus Uncertainty approach to model and analyze a full spectrum of break sizes, including small, intermediate, and large breaks, using a single computer code and input model, incorporating random sampling and advanced statistical procedures to ensure compliance with 10 CFR 50.46 criteria, and is customizable for various reactor designs.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Ease of manufacture
If a conservative deterministic approach is used to analyze Small Break LOCA, then the analysis is simple and straightforward, but it cannot provide comprehensive uncertainty assessment and is not applicable to Large Break LOCAs
Solution Approach 1:
The patent changes the analytical approach from deterministic to probabilistic by introducing uncertainty parameters and using Monte Carlo sampling methods. This allows the same code to handle both small and large break LOCAs with comprehensive uncertainty assessment while maintaining computational feasibility through systematic parameter variation and statistical analysis.
2Reliability
If a Best-Estimate Plus Uncertainty method is used to analyze Large Break LOCA, then comprehensive uncertainty assessment is achieved, but the analysis complexity increases significantly and it cannot be applied to Small Break LOCAs
Solution Approach 1:
The patent creates a universal safety analysis code that can handle both Small Break and Large Break LOCAs using the same Best-Estimate Plus Uncertainty methodology. The code incorporates modular uncertainty assessment capabilities that can be applied across different break scenarios, eliminating the need for separate analysis methods while maintaining comprehensive uncertainty evaluation.
Solution Approach 2:
The patent segments the uncertainty analysis into distinct components (input uncertainties, model uncertainties, and output uncertainties) that can be systematically evaluated and combined. This segmentation allows complex uncertainty assessment to be broken down into manageable steps that can be applied consistently across different LOCA scenarios.
3Device complexity
If intermediate breaks are not analyzed based on simplistic engineering arguments, then the analysis scope is reduced and simpler methods can be used, but comprehensive safety assessment across all break sizes is not achieved
Solution Approach 1:
The patent extends the Best-Estimate Plus Uncertainty methodology to cover the full spectrum of break sizes including intermediate breaks. The universal code structure allows seamless analysis across small, intermediate, and large breaks without requiring separate methodologies, thereby achieving comprehensive safety assessment while maintaining methodological consistency.
Data Source
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AI summary
This invention relates to a computational system and method for performing a safety analysis of a postulated Loss of Coolant Accident in a nuclear reactor for a full spectrum of break sizes including various small, intermediate and large breaks. Further, modeling and analyzing the postulated small break, intermediate break and large break LOCAs are performed with a single computer code and a single input model properly validated against relevant experimental data. Input and physical model uncertainties are combined following a random sampling process, e.g., a direct Monte Carlo approach (ASTRUM-FS) and advanced statistical procedures are utilized to show compliance with Nuclear Regulatory Commission 10 CFR 50.46 criteria.