Transient performance of China supercritical water-cooled reactor (SCWR) with the rated electric power of 1000 MWel (CSR1000) core during some typical transients, such as control rod (CR) ejection and uncontrolled CR withdrawal, is analyzed and evaluated with the coupled three-dimensional neutronics and thermal-hydraulics SCWR transient analysis code. The 3D transient analysis shows that the maximum cladding surface temperature (MCST) retains lower than safety criteria 1260 °C during the process of CR ejection accident, and the MCST retains lower than safety criteria 850 °C during the process of uncontrolled CR withdrawal transient. The safety of CSR1000 core can be ensured during the typical transients under the salient fuel temperature and water density reactivity feedback and the essential reactor protection system.
Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients
Manuscript received July 2, 2018; final manuscript received September 29, 2018; published online January 24, 2019. Assoc. Editor: Mark Anderson.
- Views Icon Views
- Share Icon Share
- Cite Icon Cite
- Search Site
Lianjie, W., Di, L., and Wenbo, Z. (January 24, 2019). "Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients." ASME. ASME J of Nuclear Rad Sci. January 2019; 5(1): 011010. https://doi.org/10.1115/1.4041693
Download citation file:
- Ris (Zotero)
- Reference Manager