Abstract
During pre-conceptual design of supercritical water-cooled reactor (SCWR), assembly design is very important and affects core performance. Coupled neutronics and thermal–hydraulics analysis is required for dramatic changes of water density in SCWR. Annular fuel assembly is optimized from the point of view of neutronics and thermal–hydraulics performance using three-dimensional coupling code. Three-dimensional diffusion calculation for annular fuel assembly is carried out using FENNEL-N. Pin power distribution is obtained. With these power, SUBSC is used to perform sub-channel analysis. The effects of fuel rod distance and gap between fuel rods and assembly box on assembly performance are researched in the coupled analysis. Results have shown that increasing fuel rod distance and rod-to-box gap will increase kinf and assembly power peaking factor. It is also shown in the results that heating heterogeneity of sub-channels plays a big role in assembly thermal performance and adding grid will flatten coolant outlet temperature as well as decrease maximum cladding surface temperature. Safety analysis of annular fuel assembly shows that the assembly is safe from the point of view of neutronics.
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Zhao, C., Wang, K., Cao, L., Wu, H., Zheng, Y. (2017). Coupled Neutronics and Thermal–Hydraulics Analysis of Annular Fuel Assembly for SCWR. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2314-9_8
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DOI: https://doi.org/10.1007/978-981-10-2314-9_8
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