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소듐냉각고속로 상부내부구조물 열스트라이핑 거동 수치해석 연구
최선락(S.R. Choi),김대희(D. Kim),정요한(Y. Jung),최석기(S.K. Choi),한지웅(J.W. Han) 한국전산유체공학회 2019 한국전산유체공학회지 Vol.24 No.2
The Korea Atomic Energy Research Institute (KAERI) has performed a reactor design with the final goal of constructing the PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor). The main objective of the PGSFR is to verify TRU metal fuel performance, reactor operation, and transmutation ability of high-level wastes. In the PGSFR, each subassembly has an independent flow path and is separately assigned a flow rate. Therefore, outlet temperatures between adjacent subassemblies are different from each other. Coolant mixing with different temperatures causes temperature fluctuations in a structure surface near the core exit. This phenomenon is called thermal striping, which can induce periodic thermal fatigues and deteriorate the integrity of the structures. The thermal striping in the UIS (upper internal structure) of the PGSFR is evaluated by the LES model. This model is employed to characterize fast turbulent vortices generated from the core exit. Temperature fluctuation is observed along a mixing region between two adjacent assemblies. The maximum temperature fluctuation on the solid surface occurs at the CRDM guide tube tip of the outer control assembly in the core outward direction. The maximum RMS value of the temperature fluctuation at the solid surface is 18.3% of the temperature difference. The present CFD analysis will be employed to evaluate creep-fatigue damage due to the temperature fluctuation cycles in the UIS.