Axial-offset analysis in iPWR by developing the neutronic/thermal-hydraulic core simulator based on coarse-mesh methods. (February 2023)

• Record Type: Journal Article
• Authors: Kolali, Ali; Naghavi dizaji, Davod; Ghafari, Mohsen; Vosoughi, Naser
• Is Part Of: Annals of nuclear energy. Volume 181(2023)
• Publication Date: 2023-02
• Subjects: Nodal expansion method -- Single heated channel -- Axial-offset -- Small modular reactor -- Integrated PWR; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2022.109566
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: A neutronic/thermal–hydraulic simulator has been developed based on coarse mesh methods to calculate AO for a Small Modular Reactor. Average Current Nodal Expansion Method (ACNEM) and Single Heated Channel (SHC) method are considered as the neutronic and the TH simulator. Macroscopic cross-sections were generated by cell calculation module corresponding to reactor operation conditions. The results demonstrate that the AO variation remains in a safe and standard operating region for SMART reactor. Abstract: Axial-Offset (AO), as an important operational parameter, should be monitored in the load-following procedure due to the safety limits related to xenon oscillation and axial peaking factor in a nuclear power plant. In this study, to calculate AO for a Small Modular Reactor, a neutronic/thermal–hydraulic simulator has been developed based on coarse mesh methods. In this simulator, the average current nodal expansion method and the single heated channel approach have been used for neutronic and thermal–hydraulic analysis, respectively. The developed simulator is verified by the IAEA-3D model and thermal–hydraulic benchmark model. As the iPWR small modular reactor case study, SMART reactor has been simulated, and the neutronic and thermal–hydraulic parameters have been calculated. For investigation of AO behavior during power changes, the regulating bank repositioning approach is employed, and the reactor core characteristics are estimated by a developed simulator. The results demonstrate that the AO variation remains in a safe and standard operating region for SMART reactor.