Analysis of SMR Reactor Coolant System in APROS
Abstract The reactor coolant system (RCS) is the primary system of the nuclear power plant primary cycle. Some small module reactors (SMR) applied once-through steam generator and integrated reactor vessel. The characteristic of these reactors differs widely from the tradition nuclear power plant. APROS Nuclear simulation and analysis software, with the Comprehensive plant model covering reactor island, turbine island, electrical and automation systems, has been successfully used in a series of major nuclear power plant projects, including power upgrade, modernization, safety improvement, and new plant projects. A reactor coolant system model of SMR that contains both process and control elements is developed and simulated using APROS. Steady states analysis is conducted under different power load and both force/natural cycle. Analysis of Transient condition including increasing/decreasing power load and force/natural circulation switching is also conducted to acquire dynamic thermal hydrate parameter. Reference and guidance can be provided for system optimization and safety analysis.
Authors
- Cai Zhiyun
- Shuren Wang (ORCID: https://orcid.org/0000-0001-5490-2825)
- Ye Zhu (ORCID: https://orcid.org/0000-0001-8609-0171)
- Minghao Liu (ORCID: https://orcid.org/0000-0003-2708-9730)
- Liao Xian-wei
Institutions
- China General Nuclear Power Corporation (China) (CN)
Publication Details
- Published
- 2024-08-04
- DOI
- https://doi.org/10.1115/icone31-131299
- Citations
- 1
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 1.30