Bell-ring vibration response of nuclear containment vessel with attached masses under earthquake motion

1976 ◽  
Vol 38 (3) ◽  
pp. 475-493 ◽  
Author(s):  
K. Shiraki ◽  
Y. Kajimura ◽  
H. Shibata ◽  
T. Kawakatsu
Keyword(s):  
Vibration Response ◽  
Containment Vessel ◽  
Earthquake Motion ◽  
Nuclear Containment ◽  
Bell Ring

Computational Modal Analyses of a Steel Nuclear Containment Vessel

2014 ◽  
Vol 490-491 ◽  
pp. 625-628
Author(s):  
Chun Lai Tian ◽  
Lin Yang ◽  
Rui Chang Zhao
Keyword(s):  
Finite Element ◽  
Shell Element ◽  
Element Model ◽  
Element Analysis ◽  
Software Cost ◽  
Containment Vessel ◽  
Nuclear Containment ◽  
Computational Analyses ◽  
Deformation Area ◽  
The Finite Element Model

In order to obtain frequencies and modal shapes of a nuclear containment vessel, the computational analyses have been carried out through free structure finite element analysis software. The finite element model of the vessel is built with shell element and solved by the type of the dynamics frequency solver. Results show that mainly deformation area is on the vessels cylindrical shell and the maximum displacements occur at its center. Compared with the design validation values, the frequencies obtained are a little lower. It may be because that the model built here is a completely vessel shell without any hatches or attachments. It is provided that a reliable method of computational structural analyses for the nuclear containment without commercial software cost.

Investigation of Mechanical Properties and Ductile-Brittle Transition Behaviors of SA738Gr.B Steel Used as Reactor Containment

2019 ◽  
Vol 795 ◽  
pp. 66-73
Author(s):  
Ya Lin Zhang ◽  
Hu Hui
Keyword(s):  
Fracture Toughness ◽  
Master Curve ◽  
Steel Plate ◽  
Reference Temperature ◽  
Impact Performance ◽  
Brittle Transition ◽  
Containment Vessel ◽  
Master Curve Method ◽  
Nuclear Containment ◽  
Curve Method

The low temperature tensile properties, Charpy-V notch impact performance and fracture toughness of SA738Gr.B steel plate for domestic CAP1400 containment vessel were tested. On this basis, the reference temperature T0 of the master curve method was obtained. The fracture toughness distribution of the steel in the whole ductile-brittle transition zone is predicted and its applicability is verified by the theoretical basis of the master curve method. The results show that the reference temperature of SA738Gr.B steel master curve method is-123.6 °C. The master curve method is appropriate for SA738Gr.B steel with domestic nuclear containment vessel.

Three-Dimensional Finite Element Analysis of a Scale Model Nuclear Containment Vessel

1986 ◽  
Vol 108 (3) ◽  
pp. 320-329
Author(s):  
G. Derbalian ◽  
G. Fowler ◽  
J. Thomas
Keyword(s):  
Finite Element Analysis ◽  
Finite Element ◽  
Ultimate Strength ◽  
Three Dimensional ◽  
Scale Model ◽  
Element Analysis ◽  
Containment Vessel ◽  
Nuclear Containment ◽  
Dimensional Finite Element ◽  
Three Dimensional Finite Element

Current design procedures for nuclear containment vessels are based on elastic analyses. Though such techniques are adequate under normal operating conditions, if the potential risks associated with extreme environments or accident conditions are to be assessed, knowledge of the ultimate capacity of the containment structure is essential. A key technical question is whether penetrations, such as personnel hatches, weaken the containment structure. In this paper, the maximum pressure sustained by a scale model, steel, nuclear containment vessel with a penetration is determined using a three-dimensional finite element analysis. To assess containment strength, a clean shell is analyzed in closed form for its ultimate strength, and the solution is then compared with finite element results for a structure that has a penetration. The comparison shows that the personnel hatch penetration does not reduce the ultimate strength of the containment structure. In this paper, it is assumed that the materials have no flaws and welded joints are perfectly bonded. Cracks in the structure, which would degrade its strength, are not considered.

scholarly journals Effect of the Young modulus variability on the mechanical behaviour of a nuclear containment vessel

2010 ◽  
Vol 240 (12) ◽  
pp. 4051-4060 ◽  
Author(s):  
T. de Larrard ◽  
J.B. Colliat ◽  
F. Benboudjema ◽  
J.M. Torrenti ◽  
G. Nahas
Keyword(s):  
Mechanical Behaviour ◽  
Young Modulus ◽  
Containment Vessel ◽  
Nuclear Containment

Shaking Table Tests and Numerical Simulation Analysis of a 1:15 Scale Model Reinforced Concrete Containment Vessel

2013 ◽  
Author(s):  
Xiaolei Wang ◽  
Dagang Lu ◽  
Gangling Hou
Keyword(s):  
Numerical Simulation ◽  
Reinforced Concrete ◽  
Simulation Analysis ◽  
Safety Margin ◽  
Shaking Table ◽  
Scale Model ◽  
Shaking Table Tests ◽  
Ground Acceleration ◽  
Containment Vessel ◽  
Earthquake Motion

In order to verify the seismic capacity of reinforced concrete containment vessel (RCCV) under the design earthquake level of SL-2 (peak acceleration 0.25g), shaking table tests of a 1:15 model RCCV are carried out. The El Centro earthquake motion record, the Taft earthquake motion record as well as an artificial earthquake acceleration are employed as the input excitations. There are three load cases for each test stage, with the peak ground acceleration (PGA) being 0.1g, 0.2g and 0.3g, respectively, corresponding to 0.088g, 0.175g and 0.263g for the prototype RCCV structure because of the acceleration ratio of 1.14. The test results indicate that under the earthquake excitation of the acceleration peak 0.1g, 0.2g and 0.3g, the tensile strains at monitoring points on the cylinder don’t reach the cracking level. Using the general-purpose nonlinear finite element analysis program ANSYS, a three-dimensional (3D) model of the scaled model reinforced concrete containment vessel is modeled. The numerical simulation analysis results could match the results of the tests very well. It is shown by the results of the shaking table tests that the model RCCV is still within the elastic range as a whole. In order to analyze the yield displacement of the RCCV, a static nonlinear pushover analysis of the RCCV is carried out. The result shows that the RCCV had sufficient seismic safety margin.

Sign in / Sign up

Export Citation Format

Share Document