Abstract In this study, the probabilistic internal pressure fragility analysis was performed by using the non-linear finite element analysis method. The target structure is one of the containment buildings of typical domestic pressurized water reactors(PWRs). The 3-dimensional finite element model of the containment building was developed with considering the large equipment hatches. To consider uncertainties in the material properties and structural capacities, we performed the sensitivity analysis of the ultimate pressure capacity with respect to the variation of four important uncertain parameters. The results of the sensitivity analysis were used to the selection of the probabilistic variables and the determination of their probabilistic parameters. To reflect the present condition of the tendon pre-stressing force, the data of the pre-stressing force acquired from the in-service inspections of tendon forces were used for the determination of the median value. Two failure modes(leak, rupture) were considered and their limit states were defined to assess the internal pressure fragility of target containment building. The internal pressure fragilities for each failure mode were evaluated in terms of median internal pressure capacity, high confidence low probability of failure(HCLPF) capacity, and fragility curves with respect to the confidence levels. The HCLPF capacity was 115.9 psig for leak failure mode, and 125.0 psig for rupture failure mode.
[1]
Daegi Hahm,et al.
Assessment of the Internal Pressure Fragility of the CANDU Type Containment Buildings using Nonlinear Finite Element Analysis
,
2010
.
[2]
Ronald L. Iman,et al.
Risk methodology for geologic disposal of radioactive waste: small sample sensitivity analysis techniques for computer models, with an application to risk assessment
,
1980
.
[3]
E. Oñate,et al.
A plastic-damage model for concrete
,
1989
.
[4]
Hsuan-Teh Hu,et al.
Ultimate analysis of PWR prestressed concrete containment subjected to internal pressure
,
2006
.
[5]
Jong-Sung Sim,et al.
An Ultimate Pressure Capacity Assessment of Prestressed Concrete Containment Vessel Considering Non-symmetric Factors
,
2004
.
[6]
Sun-Hoon Kim.
Three-Dimensional Structural Analysis System for Nuclear Containment Building
,
2010
.
[7]
Jeeho Lee,et al.
Plastic-Damage Model for Cyclic Loading of Concrete Structures
,
1998
.
[8]
Hong Pyo Lee,et al.
Shell finite element of reinforced concrete for internal pressure analysis of nuclear containment building
,
2011
.