Peach Bottom Instability Analysis with a RELAP5/PARCSv2.7 Detailed Thermal-hydraulic-Neutronic Model
In this work, BWR stability analysis was performed on an operating point (PT_UPV) of Peach Bottom NPP which is inside the exclusion region in the operating power-flow map. The simulation was made with the coupled code RELAP5-MOD3.3/PARCSv2.7. This point is achieved departing from test point 3 by a control rod movement as it is usually performed in Nuclear Power Plants. The thermal-hydraulic model is a detailed model that includes all the reactor vessel components: jet pumps, recirculation pumps, downcomer, reactor core and also the separator and the dryer. The reactor core has been modeled with 72 thermal-hydraulic channels, 71 represent the active core and 1 represent the core bypass. The reactor core thermal-hydraulic to neutronic representation (mapping) has been divided in four quadrants according to the first and second power harmonics (Lambda modes) obtained previously with the MODKIN code. This mapping was chosen in order not to condition the oscillation pattern. The transient starts with this control rod movement. The calculated results show that point PT_UPV is an unstable point and the obtained relative axial power distribution shows a bottom-peaked profile, which is characteristic of unstable cores.
BWR instabilities coupled codes Lambda modes
A. Abarca T. Barrachina R. Miró G. Verdú
Institute for Industrial, Radiophysical and Environmental Safety (ISIRYM) Universitat Politècnica de València (UPV) Camí de Vera s/n, 46021 València, Spain
国际会议
上海
英文
2193-2208
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）