Analysis and optimization of operating characteristics for integrated pressurized water reactor IP200
• A model was developed to analyze the operational characteristics of IPWR. • The IPWR design indicators of safety and maneuverability have been evaluated under typical operating conditions. • The Multi-population genetic optimization algorithm was employed to optimize operational strategies of IPWR. The integrated pressurized water reactor exhibits superior performance in terms of safety, economy, and modular implementation. However, the structural differences of the integrated pressurized water reactor make its operation more complex compared to traditional pressurized water reactors. This paper established a model for the integrated pressurized water reactor IP200 and analyzed the characteristics of typical operating conditions. Furthermore, the optimization of operational strategies for typical transient process was carried out based on intelligent algorithms. Specifically, the transient operational characteristics of the IP200 was analyzed by nuclear-thermal coupling method. During the step load change under forced circulation, the IP200 could achieve a rapid response within 40 s and reach a new stable state. However, the transition time during the transition from forced circulation to natural circulation was 461 s, exceeding the maneuverability indicators. Therefore, the paper used a multi-population genetic algorithm to optimize the operational strategies and obtained the optimal transition time. Under optimized operational strategy, the initial conversion power, average reactor temperature, and shut-off interval time of main coolant pump were 31.78 %FP, 572.48 K, and 0 s, respectively. The conversion time was reduced to 381 s, which was 17.4 % shorter than before, achieving thermal safety and maneuverability requirements.
Authors
- Genglei Xia
- Minjun Peng (ORCID: https://orcid.org/0000-0001-5867-1972)
- Li Ren (ORCID: https://orcid.org/0000-0002-4003-8826)
- Xu Yang (ORCID: https://orcid.org/0000-0003-4252-1667)
- Yuandong Zhang (ORCID: https://orcid.org/0000-0002-6242-8753)
- Hao Xu (ORCID: https://orcid.org/0000-0002-8134-6892)
Institutions
- Harbin Engineering University (CN)
- Wuhan Ship Development & Design Institute (CN)
Publication Details
- Journal
- Annals of Nuclear Energy
- Published
- 2025-06-24
- DOI
- https://doi.org/10.1016/j.anucene.2025.111682
- Citations
- 2
- Primary Topic
- Nuclear Engineering Thermal-Hydraulics
- Type
- article
- Field-Weighted Citation Impact
- 9.99