Effects of Torus Wall Flexibility on Forces in the Mark I Boiling Water Reactor Pressure Suppression System. Final Report

摘要

The FY78 results are summarized of a program to investigate, through analytical models, the effects of wall flexibility on hydrodynamically induced loads in the torus-shaped pressure suppression chamber of a Mark I boiling water reactor, both in the event of a safety relief valve (SRV) discharge and a hypothetical loss-of-coolant accident (LOCA). Two-dimensional and three-dimensional analytical models for these two events were created by using the Monticello nuclear plant's geometry and finite element computer codes. Initial two-dimensional results were documented in the FY77 report (Lawrence Livermore Laboratory, UCRL--52506); those two-dimensional results are extended here by varying the pulse amplitudes and conducting nonlinear analyses for comparison with the linear analyses. Finally, three-dimensional analyses are conducted for the SRV discharge and LOCA chug problems. (ERA citation 04:038821)