OECD/NEA ROSA-2 Project (7) A preliminary 3D Steam Flow Analysis for CET Behavior simulation during LSTF SBLOCA Experiment

Dwi Irwanto; Akira SATOU; Takeshi TAKEDA; Hideo NAKAMURA

doi:10.11561/aesj.2013s.0.279.0

2013 Annual Meeting

セッションID: N51

DOI https://doi.org/10.11561/aesj.2013s.0.279.0

会議情報

主催: Atomic Energy Society of Japan

OECD/NEA ROSA-2 Project

(7) A preliminary 3D Steam Flow Analysis for CET Behavior simulation during LSTF SBLOCA Experiment

*Irwanto Dwi, SATOU Akira, TAKEDA Takeshi, NAKAMURA Hideo

著者情報

キーワード: OECD/NEA ROSA-2 Project, LSTF (Large Scale TEst Facility), SBLOCA (Small Break Loss of Coolant Accident), CET (Core Exit Temperature), CFD (Computational Fluid Dynamic)

会議録・要旨集認証あり

詳細

抄録

3D steam flow within simulated fuel bundle of LSTF (Large Scale Test Facility); a PWR system simulator, has been investigated by CFD analysis with ANSYS FLUENT code to clarify influences of the steam flow on CET (Core Exit Temperature) response. A portion of LSTF core was modeled and simulation was carried out at a certain time during SBLOCA (Small Break Loss of Coolant Accident). The CET response in terms of 3D steam flow is discussed through such measured and calculated parameters as temperature, velocity and flow behavior in the core.

責任著者(Corresponding author)

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