Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan
2013 Annual Meeting
Session ID : N51
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OECD/NEA ROSA-2 Project
(7) A preliminary 3D Steam Flow Analysis for CET Behavior simulation during LSTF SBLOCA Experiment
*Dwi IrwantoAkira SATOUTakeshi TAKEDAHideo NAKAMURA
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Abstract
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.
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© 2013 Atomic Energy Society of Japan
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