Fragility analysis of prestressed concrete containment under severe accident condition

2019 ◽  
Vol 131 ◽  
pp. 242-256 ◽  
Author(s):  
Song Jin ◽  
Zhongcheng Li ◽  
Tianyun Lan ◽  
Jinxin Gong
2015 ◽  
Vol 2015.28 (0) ◽  
pp. _228-1_-_228-3_
Author(s):  
Susumu Yamashita ◽  
Kazuyuki Tokushima ◽  
Masaki Kurata ◽  
Kazuyuki Takase ◽  
Hiroyuki Yoshida

2017 ◽  
Vol 316 ◽  
pp. 63-74 ◽  
Author(s):  
Jianfeng Mao ◽  
Xiangqing Li ◽  
Shiyi Bao ◽  
Lijia Luo ◽  
Zengliang Gao

2016 ◽  
Vol 711 ◽  
pp. 879-884
Author(s):  
Jean Michel Torrenti

The prestressed concrete confinement vessel is the third and last barrier in Nuclear Power Plants (NPP). In case of a severe accident (loss of cooling agent of the reactor for instance), pressure and temperature will increase in the nuclear vessel (0,5 MPa and 180°C during 2 weeks). Due to elevated temperatures, the evolution of basic creep will be accelerated. In this case, due to internal pressure, some tensile stresses could appear in specific parts of the structure and induce cracking. The modelling of basic creep and its couplings with temperature is very important for the safety of the structure (tightness of the concrete vessel). Here we present a model considering the following elements: a coupling between creep and damage is introduced, kinetics of basic creep is affected by temperature by the means of an Arrhenius thermo-activation, damage due to the increase of temperature is taken into account. The model is compared with the available experimental results. This work is a part of the MACENA project.


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