Reevaluation of failure criteria location and novel improvement of 1/4 PCCV high fidelity simulation model under material uncertainty quantifications

• Published in: Nuclear engineering and technology Vol. 55; no. 9; pp. 3493 - 3505
• Main Authors: Bu-Seog Ju, Ho-Young Son
• Format: Journal Article
• Language: Korean
• Published: 2023
• Subjects: Statistical analysis; Pressure capacity; Reactor containment building; Free-field; Prestressed concrete containment vessel; Material uncertainties
• ISSN: 1738-5733; 2234-358X

Reactor containment buildings serve as the last barrier to prevent radioactive leakage due to accidents and their safety is crucial in overpressurization conditions. Thus, the Regulatory Guide (RG) 1.216 has mentioned the global strain as one of failure criteria in the free-field for cylindrical prestressed concrete containment vessels (PCCV) subject to internal pressure. However, there is a limit that RG 1.216 shows the free-field without the specific locations of failure criteria and also the global strain corresponding to only azimuth 135° has been mentioned in NUREG/CR-6685, regardless of the elevations of the structure. Therefore, in order to reevaluate the failure criteria of the 1:4 scaled PCCV, the high fidelity simulation model based on the experimental test was significantly validated in this study, and it was interesting to find that the experimental and numerical result was very close to each other. In addition, for the consideration of the material uncertainties, the Latin hypercube method was used as a statistical approach. Consequently, it was revealed that the radial displacements of various azimuth area such as 120°, 135°, 150°, 180° and 210° at elevations 4680 mm and 6,200 mm can represent as the global deformation at the free-field, obtained from the statistical approach.