The purpose of this study is to identify hydrodynamic loads due to steam condensation acting on the Suppression Pool (S/P) in Primary Containment Vessel (PCV) of Advanced-Boiling Water Reactor (ABWR) by using general-purpose analysis code, ANSYS™. The source load methodology has been used to evaluate the hydrodynamic loads, which are classified into condensation oscillation (CO) and chugging (CH). When setting the design source from the confirmation test, the calculation method due to the eigenfunction of the cylindrical coordinate system was used. Since, there were various limitations in the previous approaches, a new analysis approach has been expected. In this study, the pool of ABWR horizontal-vent confirmatory test facility is modeled with the ANSYS™ acoustic elements. The calculation results are in good agreement with the test pressure oscillations. It is confirmed that the proposed approach can create the design source enveloping the PSD of test results.
- Nuclear Engineering Division
Evaluation of Dynamic Loads due to Steam Condensation in Boiling Water Reactor ABWR Containment
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Shioyama, T, Nakane, M, Miyagawa, T, Ukai, M, Watanabe, M, & Hagiwara, T. "Evaluation of Dynamic Loads due to Steam Condensation in Boiling Water Reactor ABWR Containment." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues. Prague, Czech Republic. July 7–11, 2014. V001T03A007. ASME. https://doi.org/10.1115/ICONE22-30141
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