CFD Simulation for Flow Behavior in Boiling Water Reactor Vessel and Upper Pool under Decommissioning Condition
In order to respond the policy decision of non-nuclear homes, Tai Power Company (TPC) will provide the decommissioning project of Kuosheng Nuclear power plant (KSNPP) to meet the regulatory requirement in near future. In this study, the computational fluid dynamics (CFD) methodology has been employed to develop a flow prediction model for boiling water reactor (BWR) with upper pool under decommissioning stage. The model can be utilized to investigate the flow behavior as the vessel combined with upper pool and continuity cooling system. At normal operating condition, different parameters are obtained for the full fluid area, including velocity, mass flow, and mixing phenomenon in the reactor pressure vessel (RPV) and upper pool. Through the efforts of the study, an integrated simulation model will be developed for flow field analysis of decommissioning KSNPP under normal operating condition. It can be expected that a basis result for future analysis application of TPC can be provide from this study.
Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1316552Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 670
 Institute of Nuclear Energy Research, “Safety Evaluated Report: Thermal Analysis of Dry Storage and NPP Outage Units by CFD Methodology,” NRD-SER-99-06 (2011).
 Yung-Shin Tseng, Chih-Hung Lin, Yng-Ruey Yuann, Jong-Rong Wang and F. Peter Tsai, “Analyzing the Alternative Shutdown Cooling Behaviors for Chinshan Nuclear Power Plant Using CFD Simulation,” Annals of Nuclear Energy, Vol. 38 (11), pp.2557-2568 (2011).
 Yu-Ting Ku, Yung-Shin Tseng, Chih-Wei Su, Jong-Rong Wang, Chunkuan Shih, “The Thermal Hydraulic Behavior in Core Inlet Region of BWR with the Inadvertent Startup of HPCI,” NUTHOS-9, Kaohsiung, Taiwan (2012).
 Sahoshih Ma, Susen Hsu, Yung-Shin Tseng, “Evaluation of the Asymmetric Effects on Core Thermal Limits for the Inadvertent Cold Coolant Injection Transient in Chinshan BWR-4 Plant,” Annals of Nuclear Energy, Volume 78, pp.15-25 (2015).
 Jan-Ru Tang, Chih-Chung Chung, Yung-Shin Tseng, “Analysis of the Inadvertent Start of HPCI Event for the Chinshan Nuclear Power Plant with CSAU Approach,” EDSM2010-ICNMM2010, Montreal, Canada (2010).
 ANSYS, FLUENT V12 User’s Guide, ANSYS Inc. (2009).
 J. Mahaffy, B. Chung, C. Song, et al., “Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications - Revision” Organization for Economic Co-Operation and Development, NEA/CSNI/R (2014)11.
 J. P. Van Doormaal, G. D. Raithby, “Enhancements of the SIMPLE Method for Predicting Incompressible Fluid Flows,” Numerical Heat Transfer, vol. 7, issue 2, pp.147-163 (1984).