TRAC-BF1 THREE-DIMENSIONAL BWR VESSEL THERMAL-HYDRAULIC AND ANSYS STRESS ANALYSES FOR BWR CORE SHROUD CRACKING

摘要

TRAC-BF1 transient analysis for a General Electric boiling water reactor (BWR/2) was performed for a main steam line break (MSLB) event and a recirculation line break (RLB) transient to determine the susceptibility of the core shroud to geometric alteration when intergranular stress corrosion cracking (IGSCC) is present at the upper H3 and lower H7 core shroud weld locations. The TRAC-BF I model developed for the MSLB transient utilized a 1-D vessel component model with both main steam lines rupturing at transient initiation. A detailed ANSYS model was developed to find the forces imposed at the upper H3 weld positions.