1
|
Development of Automatic Crack Growth Simulation Program Based on Finite Element Analysis. APPLIED SCIENCES-BASEL 2022. [DOI: 10.3390/app12063075] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/01/2023]
Abstract
A crack growth simulation program based on the advanced iterative-finite element method (AI-FEM) was developed to predict realistic crack growth of structures. The developed program was suggested to calculate the exact stress intensity factor for arbitrary structures by regenerating the crack tip mesh as the crack grows. The main advantages of the developed program are to estimate each different crack growths along the crack tip line and to simulate the cracking transition from a surface crack to a through-wall crack under a complex stress field. For these purposes, the sensitivity analyses were performed for various influence variables on stress intensity factors, such as element types and crack dimensions. Based on the results of sensitivity analyses, the appropriate criteria for crack tip modeling to be used in AI-FEM were suggested to calculate sufficient converged SIF. The program developed in this research was validated through stress corrosion crack growth and natural crack growth examples including cracking transition, and it was confirmed that the program simulates crack growth well and has reasonable methods for cracking transition.
Collapse
|
2
|
Rothleder BM, Poetschat GR, Faught WS, Eich WJ. The Potential for Expert System Support in Solving the Pressurized Water Reactor Fuel Shuffling Problem. NUCL SCI ENG 2017. [DOI: 10.13182/nse88-a23577] [Citation(s) in RCA: 15] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- B. M. Rothleder
- Science Applications International Corporation, 1710 Goodridge Drive, McLean, Virginia 22102
| | - G. R. Poetschat
- Science Management Corporation–ESMI, 12655 SW Center St., Suite 380, Beaverton, Oregon 97005
| | - W. S. Faught
- IntelliCorp, 1975 El Camino Real West, Mountain View, California 94040
| | - W. J. Eich
- Electric Power Research Institute, 3412 Hillview Avenue, Palo Alto, California 94303
| |
Collapse
|
3
|
Stillman JA, Chao YA, Downar TJ. The Optimum Fuel and Power Distribution for a Pressurized Water Reactor Burnup Cycle. NUCL SCI ENG 2017. [DOI: 10.13182/nse89-a23685] [Citation(s) in RCA: 33] [Impact Index Per Article: 4.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- J. A. Stillman
- Commonwealth Edison Company, Nuclear Fuel Services, Chicago, Illinois 60603
| | - Y. A. Chao
- Westinghouse Commercial Nuclear Fuel Division, P. O. Box 3912, Pittsburgh, Pennsylvania 15230-3912
| | - T. J. Downar
- Purdue University, School of Nuclear Engineering, West Lafayette, Indiana 47907
| |
Collapse
|
4
|
Rozon D, Beaudet M. Canada Deuterium Uranium Reactor Design Optimization Using Three-Dimensional Generalized Perturbation Theory. NUCL SCI ENG 2017. [DOI: 10.13182/nse92-a23919] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- D. Rozon
- Groupe d’Analyse Nucléaire, lnstitut de Génie Énergétique, École Polytechnique de Montréal Montréal, Québec, Canada H3C 3A7
| | - M. Beaudet
- Groupe d’Analyse Nucléaire, lnstitut de Génie Énergétique, École Polytechnique de Montréal Montréal, Québec, Canada H3C 3A7
| |
Collapse
|
5
|
Ibrahim A. Transuranium isotopes production and their effect on the three-dimensional core calculation. ANN NUCL ENERGY 1993. [DOI: 10.1016/0306-4549(93)90060-3] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
|
6
|
Zavaljevski N. A model for fuel shuffling and burnable absorbers optimization in low leakage PWRs. ANN NUCL ENERGY 1990. [DOI: 10.1016/0306-4549(90)90055-i] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
|
7
|
Kim HC, Hsiao MY, Levine SH. Increased-Discharge-Burnup Method for Multicycle Reload Design. NUCL TECHNOL 1989. [DOI: 10.13182/nt89-a34297] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Hyong Chol Kim
- The Pennsylvania State University Department of Nuclear Engineering, 231 Sackett Building University Park, Pennsylvania 16802
| | - Ming-Yuan Hsiao
- The Pennsylvania State University Department of Nuclear Engineering, 231 Sackett Building University Park, Pennsylvania 16802
| | - Samuel H. Levine
- The Pennsylvania State University Department of Nuclear Engineering, 231 Sackett Building University Park, Pennsylvania 16802
| |
Collapse
|
8
|
Evaluation of leak flow rate and jet impingement related to leak before break. NUCLEAR ENGINEERING AND DESIGN 1989. [DOI: 10.1016/0029-5493(89)90290-2] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
|