Analysis of Shell-Rupture Failure Due to Hypothetical Elevated-Temperature Pressurization of the Sequoyah Unit 1 Steel Containment Building.

摘要

Sandia National Laboratories, as part of the Containment Integrity Programs under the sponsorship of the Nuclear Regulatory Commission (NRC), has developed analytical techniques for predicting the performance of light water reactor steel containment buildings subject to loads beyond the design basis. The objective of the analysis was to determine the actual pressure capacity and the mode, location, and size of failure, where a functional definition of failure is used. The purpose of the report is to document the calculations performed to determine the pressure limits for the shell-rupture mode of failure. General failure of the containment shell is predicted by application of a failure criterion to the results from finite element structural analyses. Separate finite element models were used to evaluate the overall free-field behavior of the structure and the localized behavior at a specific penetration location.