Optimization strategy for SAM in nuclear power plants based on NSGA-II
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Sikai Zhou
Abstract
The Severe Accident Management Guide (SAMG) is an important component of nuclear safety regulations. Many studies are being conducted to optimize severe accident management (SAM) strategies. To ensure the safety of nuclear power plants, decision makers need to monitor multiple parameters with security threats. Therefore, it is particularly important to search optimal SAM strategies under different numbers of mitigation targets. The Non-dominated Sorting Genetic Algorithm-II (NSGA-II) is an evolutionary algorithm that does not require derivative differentiation and is capable of population search. In this study, a nuclear power plant accident optimization strategy is developed using the Modular Accident Analysis Program (MAAP) in conjunction with NSGA-II. The strategy enables decision makers to consider multiple mitigation objectives in a complex decision environment. Focusing on the CPR1000, this study applies the optimization strategy to automatically search for optimal mitigation strategies for small break loss of coolant accident (SBLOCA) and station blackout hot leg creep rupture accidents (SBOHLCR). Comparing the optimization results with the basic accident sequence, it is found that the reactor pressure vessel (RPV) failure time is delayed from 72,702 s to 128,730 s under SBLOCA and from 23,828 s to 28,363 s under SBOHLCR. This study has also verified that the optimal SAM strategy obtained by the strategy through dual objective optimization has better mitigation effects than a strategy that only considers one objective. This optimization strategy has the potential to be applied to other types of severe accident management studies in the future.
Funding source: The Natural Science Foundation of Fujian Province of China
Award Identifier / Grant number: No. 2020J01038
Funding source: Fundamental Research Funds for the Central Universities
Award Identifier / Grant number: No. 20720220118
Funding source: The National Natural Science Funds of China
Award Identifier / Grant number: No. 72104207
Acknowledgments
The project was supported by the Fundamental Research Funds for the Central Universities (No. 20720220118), the National Natural Science Funds of China (No. 72104207) and the Natural Science Foundation of Fujian Province of China (No. 2020J01038).
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Research ethics: Not applicable.
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Author contributions: All authors have accepted responsibility for the entire content of this manuscript and approved its submission.
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Competing interests: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: The raw data can be obtained on request from the corresponding author.
Nomenclature
- APORV
-
Area of Power-Operated Relief Valves
- BDBA
-
Beyond Design Basis Accidents
- CET
-
Core Exit Temperature
- EOP
-
Emergency Operating Procedure
- FNPP
-
Floating Nuclear Power Plant
- LB-LOCA
-
Loss of Coolant Large Break Accident
- LLOCA
-
Large-break Loss of Coolant Accident
- LOFW
-
Loss of Feed Water
- MAAP4
-
Modular Accident Analysis Program
- NSGA
-
Non-dominated Sorting Genetic Algorithm
- NSGA-II
-
Non-dominated Sorting Genetic Algorithm-II
- PORV
-
Power-Operated Relief Valves
- PWR
-
Pressurized Water Reactor
- PZR
-
Pressurizer
- RNS
-
Residual Heat Removal System
- RCP
-
Reactor Coolant Pump
- RCS
-
Reactor Coolant System
- RPV
-
Reactor Pressure Vessel
- SAG
-
Severe Accident Guideline
- SAM
-
Severe Accident Management
- SAMG
-
Severe Accident Management Guideline
- SBO
-
Station Blackout
- SBLOCA
-
Small Break Loss of Coolant Accident
- SBOHLCR
-
Station Blackout Hot Leg Creep Rupture
- SG
-
Steam Generators
- SMR
-
Small Modular Reactor
- SV
-
Safety Valve
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- Calendar of events
Articles in the same Issue
- Frontmatter
- CFD modeling of natural convection in pebble bed geometry with finite volume method
- Experimental investigation of heat transfer characteristics of inclined aluminium two phase closed thermosyphon
- Advances in triple tube heat exchangers regarding heat transfer characteristics of single and two-phase flows in comparison to double tube heat exchangers part 1
- Advances in triple tube heat exchangers regarding heat transfer characteristics of single and two-phase flows in comparison to double tube heat exchangers part 2
- Neutronic and thermal-hydraulic assessment of the TRR with new core designed based on tubular fuels
- A non-dominated discrete differential evolution for fuel loading pattern optimization of a nuclear research reactor
- CFD and machine learning based hybrid model for passive dilution of helium in a top ventilated compartment
- Optimization strategy for SAM in nuclear power plants based on NSGA-II
- Probing 6He induced reactions with nuclear level density
- An application for nonlinear heterogeneity-based isotherm models in characterization of niobium sorption on clay rocks and granite
- Calendar of events
