scholarly journals Interfacing VPSC with finite element codes. Demonstration of irradiation growth simulation in a cladding tube

2016 ◽  
Author(s):  
Anirban Patra ◽  
Carlos Tome
Keyword(s):  
Finite Element ◽  
Growth Simulation ◽  
Irradiation Growth

Automated Modeling and Crack Growth Simulation in Pressurized Thin Shell Panels With Multi-Site Damage

2003 ◽  
Author(s):  
K. V. N. Gopal ◽  
B. Dattaguru
Keyword(s):  
Finite Element ◽  
Crack Growth ◽  
Mesh Generation ◽  
Structural Integrity ◽  
Element Analysis ◽  
Automated Modeling ◽  
Growth Simulation ◽  
Crack Growth Simulation ◽  
Piping Systems ◽  
Thin Walled

The residual strength estimation of thin-walled pressurized shell structures is of relevance to pressurized thin piping systems and aged airframes for life extension programs. This requires powerful and efficient computational techniques using finite element method and numerical fracture mechanics for elastic or inelastic stress analysis and crack growth simulation. For this purpose, detailed modeling and finite element mesh generation of built-up structures like stiffened cracked thin shells is necessary and it is a computationally intensive task. Automating the entire process from geometric modeling to stress analysis and crack growth simulation (requires remeshing) vastly improves the efficiency of the computational analysis and reduces the chances of modeling and simulation errors. A geometric primitive based technique has been developed for automated modeling and meshing. The work is carried out primarily on aged fuselage shell panels but the method is applicable to other pressurized thin piping systems. This paper presents a simple and efficient computational procedure using a geometry based logic and surface mesh generation technique for automated modeling and crack growth simulation in pressurized thin-walled shells. The approach has been used to develop a structural integrity evaluator software. Finite element analysis is carried out using a commercial software, and these results are fed to the structural integrity evaluator. Some results of the nonlinear finite element analysis and elastic-plastic stable crack growth simulation in pressurized stiffened fuselage panels using this approach are presented.

Fatigue Crack Growth Simulation Using S-Version FEM: Application to Interacting Subsurface Cracks

2017 ◽  
Vol 741 ◽  
pp. 82-87 ◽  
Author(s):  
Akiyuki Takahashi ◽  
Ayaka Suzuki ◽  
Masanori Kikuchi
Keyword(s):  
Finite Element Method ◽  
Finite Element ◽  
Fatigue Crack ◽  
Fatigue Crack Growth ◽  
Crack Growth ◽  
Crack Depth ◽  
Growth Simulation ◽  
Subsurface Cracks ◽  
Crack Growth Simulation ◽  
Growth Evaluation

In this paper, fatigue crack growth simulation of interacting subsurface cracks using the s-version finite element method (SFEM) is presented. In order to evaluate the accuracy and reliability of the proximity rules published by the ASME, during the fatigue crack growth simulations, the subsurface cracks are approximated to either a single elliptical crack or semi-elliptical surface crack in accordance with the proximity rules. Then, the proximity rules are slightly modified for improving the accuracy and reliability. The results of crack depth evolution calculated by the SFEM with the use of the new proximity rules suggest that the approximation to deep cracks drastically improves the accuracy of the fatigue crack growth evaluation. Thus, the approximation to deep cracks must be a promising approach for having better evaluation of fatigue crack growth of subsurface cracks.

scholarly journals Assessment of WWER-1000 Core Baffle Form Alteration during Operation

2020 ◽  
pp. 13-20
Author(s):  
A. Chirkov ◽  
V. Kharchenko ◽  
S. Kobelsky
Keyword(s):  
Finite Element ◽  
Reactor Core ◽  
Dose Dependence ◽  
Element Analysis ◽  
Spacer Grids ◽  
The Core ◽  
Mixed Scheme ◽  
Irradiation Growth ◽  
The Finite Element Analysis ◽  
Different Temperatures

The paper illustrates the results of the computer assessment of the form alteration in WWER-1000 core baffle obtained via the solution to the coupled thermoelastoplastic task considering the strains of irradiation growth and creep. In the modeling of the contact conditions, the temperature redistribution is considered due to the incompliance of the coolant flow in the contact zone between the core baffle and in-vessel core barrel with the design conditions. The modern approaches to the modeling of strains of the irradiation growth and irradiation creep in austenite steels are used in the space-limited environment under neutron exposure and elevated temperature. The finite element analysis involves the mixed scheme of the finite element method, which allows determination of the stress-strain state with high accuracy. The calculations are performed in the two-dimensional statement for the cross-section of the core baffle with the maximum damaging dose and irradiation temperature under the condition of the generalized plane strain. The results of the calculations are presented for full-scale reactor operation and scheduled shutdown to recharge the fuel cluster at the end of core life. The data on the distribution and value of the gap between the core baffle and barrel, as well as the spacer grids of the edge fuel assemblies and reactor core baffle edges, have been obtained from the median values of the dose dependence on swelling at different temperatures in Kh18N10T austenite steel.

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