An Integrated COMUS Framework for Multi-Objective Optimization and Dynamic Uncertainty Analysis of the Pressurized Water Reactor Core Power Control System

To achieve control optimization and a performance evaluation of the pressurized water reactor core power system, a COMUS (control-oriented multi-objective optimization with dynamic uncertainty and sensitivity analysis) framework is proposed. First, the reactor core power temperature dual-channel control system is established. Subsequently, a MOPSO (multi-objective particle swarm optimization) algorithm is employed to perform the offline optimization of the controller parameters, with the aim to improve the system’s power tracking capability and transient response performance.Building upon an optimized control system, this paper combines Latin hypercube sampling (LHS) with the statistical quantitative analysis method (SQAM) to establish the SQAM-LHS method. This method is used to evaluate the propagation characteristics of the multiphysics parameter uncertainties during transient processes and their impact on the system output. Additionally, a global sensitivity analysis based on the PAWN (probabilistic analysis with numerical uncertainties) method is conducted to identify the key input parameters that affect the dynamic performance of the control system.Finally, the COMUS framework is applied to two typical operating conditions. The results show that uncertainties in the input parameters cause varying degrees of fluctuation in the output parameters. Total reactivity is the most sensitive to parameter uncertainties and exhibits more pronounced dynamic fluctuations. Near the 40% full-power level, the fuel temperature feedback coefficient is a key parameter affecting reactor core relative power, coolant temperature deviation, and fuel temperature deviation. Meanwhile, the decay constant has a significant impact on the stabilization time of total reactivity and related dynamic performance indicators.

Authors

Institutions

Publication Details

Journal
Nuclear Science and Engineering
Published
2026-08-25
DOI
https://doi.org/10.1080/00295639.2026.2713897
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00
Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
article

An Integrated COMUS Framework for Multi-Objective Optimization and Dynamic Uncertainty Analysis of the Pressurized Water Reactor Core Power Control System

Chuqi Chen, Chengwei Zhang, Zheng Li, Xiaoyu Li
Nuclear Science and Engineering
Nuclear reactor physics and engineering
article

An Integrated COMUS Framework for Multi-Objective Optimization and Dynamic Uncertainty Analysis of the Pressurized Water Reactor Core Power Control System

Chuqi Chen, Chengwei Zhang, Zheng Li, Xiaoyu Li
article en

Abstract

To achieve control optimization and a performance evaluation of the pressurized water reactor core power system, a COMUS (control-oriented multi-objective optimization with dynamic uncertainty and sensitivity analysis) framework is proposed. First, the reactor core power temperature dual-channel control system is established. Subsequently, a MOPSO (multi-objective particle swarm optimization) algorithm is employed to perform the offline optimization of the controller parameters, with the aim to improve the system’s power tracking capability and transient response performance.Building upon an optimized control system, this paper combines Latin hypercube sampling (LHS) with the statistical quantitative analysis method (SQAM) to establish the SQAM-LHS method. This method is used to evaluate the propagation characteristics of the multiphysics parameter uncertainties during transient processes and their impact on the system output. Additionally, a global sensitivity analysis based on the PAWN (probabilistic analysis with numerical uncertainties) method is conducted to identify the key input parameters that affect the dynamic performance of the control system.Finally, the COMUS framework is applied to two typical operating conditions. The results show that uncertainties in the input parameters cause varying degrees of fluctuation in the output parameters. Total reactivity is the most sensitive to parameter uncertainties and exhibits more pronounced dynamic fluctuations. Near the 40% full-power level, the fuel temperature feedback coefficient is a key parameter affecting reactor core relative power, coolant temperature deviation, and fuel temperature deviation. Meanwhile, the decay constant has a significant impact on the stabilization time of total reactivity and related dynamic performance indicators.

Nuclear Science and Engineering
North China Electric Power University (CN), Shanghai Jiao Tong University (CN), Beijing Normal University (CN), University of South China (CN)
Clean water and sanitation
Openalex Percentile: Top 6%
Nuclear reactor physics and engineering
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.