Effect of material hardening model for canister on finite element cask drop simulation for strain-based acceptance evaluation
1
조회
0
다운로드
4
인용
0
참고문헌
키워드
초록
The effect of the material hardening model of the canister on a finite element vertical cask drop simulationis investigated for the strain-based acceptance evaluation. Three different hardening models areconsidered in this paper: the isotropic hardening model, the strain rate-dependent Johnson-Cook (J-C)hardening model, and the modified J-C model which are believed to be the most accurate. By comparingthe results using the modified J-C model, it is found that the use of the J-C model provides similar orlarger stresses and strains depending on the magnitudes of the strain and strain rate. The use of theisotropic hardening model always yields larger stresses and strains. For the strain-based acceptanceevaluation, the use of the isotropic hardening model can produce highly conservative assessment results. The use of the J-C model, however, produces satisfactory results.
Abstract
The effect of the material hardening model of the canister on a finite element vertical cask drop simulationis investigated for the strain-based acceptance evaluation. Three different hardening models areconsidered in this paper: the isotropic hardening model, the strain rate-dependent Johnson-Cook (J-C)hardening model, and the modified J-C model which are believed to be the most accurate. By comparingthe results using the modified J-C model, it is found that the use of the J-C model provides similar orlarger stresses and strains depending on the magnitudes of the strain and strain rate. The use of theisotropic hardening model always yields larger stresses and strains. For the strain-based acceptanceevaluation, the use of the isotropic hardening model can produce highly conservative assessment results. The use of the J-C model, however, produces satisfactory results.
참고문헌 (27)
- U.S. Nuclear Regulatory Commission, "Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities", ~ (2020)
- U.S. Nuclear Regulatory Commission, "Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material", ~ (1989)
- ASME B&PV Code Committee, "ASME B&PV Code, Sec. III, Appendices, Nonmandatory Appendix F, Rules for Evaluation of Service Loadings with Level D Service Limits", ~ (2019)
- ASME B&PV Code Committee, "ASME B&PV Code, Sec. III, Appendices, Nonmandatory Appendix FF, Strain-Based Acceptance Criteria for Energy-Limited Events", ~ (2019)
- S. D. Snow, "Strain-based acceptance criteria for energy-limited events", Proc. ASME PVP 2009 (2009)
- C. C. Huang, "A study on dynamic impact of vertical concrete cask tipover using explicit finite element analysis procedures", Ann. Nucl. Energy, 36, pp.213~221 (2009)[DOI]
- M. Lin, "Analysis of the interactions between spent fuel pebble bed and storage canister under impact loading", Nucl. Eng. Des, 361, pp.110548~ (2020)[DOI]
- T. L. Teng, "The dynamic analysis of nuclear waste cask under impact loading", Ann. Nucl. Energy, 30, pp.1473~1485 (2003)[DOI]
- Y. S. Lee, "A study on the free drop impact of a cask using commercial FEA codes", Nucl. Eng. Des, 235, pp.2219~2226 (2005)[DOI]
- K. Sharma, "Optimization of cask for transport of radioactive material under impact loading", Nucl. Eng. Des, 273, pp.190~201 (2014)[DOI]
- D. H. Kim, "Finite element analyses and verifying tests for a shock-absorbing effect of a pad in a spent fuel storage cask", Ann. Nucl. Energy, 34, pp.871~882 (2007)[DOI]
- K. S. Kim, "Dynamic impact characteristics of KN-18 SNF transport cask-Part 1 : an advanced numerical simulation and validation technique", Ann. Nucl. Energy, 37, pp.546~559 (2010)[DOI]
- K. S. Kim, "Dynamic impact characteristics of KN-18 SNF transport cask-Part 2 : sensitivity analysis of modeling and design parameters", Ann. Nucl. Energy, 37, pp.560~571 (2010)[DOI]
- C. Y. Lin, "Nonlinear dynamic impact analysis for installing a dry storage canister into a vertical concrete cask", Int. J. Pres. Ves. Pip, 131, pp.22~35 (2015)[DOI]
- T. Y. Wu, "Dynamic response analysis of a spent-fuel dry storage cask under vertical drop accident", Ann. Nucl. Energy, 42, pp.18~29 (2012)[DOI]
- S. P. Kim, "Stress-based vs. Strain-based safety evaluations of spent nuclear fuel transport casks in energy-limited events", Nucl. Eng. Des, 355, pp.110324~ (2019)[DOI]
- G. R. Johnson, "Fracture characteristics of three metals subjected to various strains, strain rates, temperatures and pressures", Eng. Fract. Mech, 21, pp.31~48 (1985)[DOI]
- Strain-Hardening and Strain-Rate Effects in the Impact Loading of Cantilever Beams, "G. R. Cowper", Brown Univ Provid, ~ (1957)
- F. J. Zerilli, "Dislocation-mechanics-based constitutive relations for material dynamics calculations", J. Appl. Phys. Appl. Phys, 61, pp.1816~1825 (1987)[DOI]
- H. Huh, "Crash-worthiness assessment of thin-walled structures with the high-strength steel sheet", Int. J. Veh. Des, 30, pp.1~21 (2002)[DOI]
- H. Zhao, "The testing and behaviour modelling of sheet metals at strain rates from 10-4 to 104 s-1", Mater. Sci. Eng, 207, pp.46~50 (1996)[DOI]
- Jun-Min Seo, "Modification of the Johnson–Cook Model for the Strain Rate Effect on Tensile Properties of 304", 316 Austenitic Stainless Steels, 2021, pp.144(1), ~[DOI]
- J. Q. Tan, "A modified Johnson-Cook model for tensile flow behaviors of 7050-T7451 aluminum alloy at high strain rates", Mater. Sci. Eng, 631, pp.214~219 (2015)[DOI]
- G. Geng, "A modified Johnson-Cook model of 6061-T6Aluminium profile", Aust. J. Mech. Eng, pp.1~11 (2020)[DOI]
- T. Kim, "Preliminary safety analysis of criticality for dual-purpose metal cask under dry storage conditions in South Korea", Nucl. Eng. Des, 278, pp.414~421 (2014)[DOI]
- 고재훈, "Shielding Analysis of Dual Purpose Casks for Spent Nuclear Fuel Under Normal Storage Conditions", Nuclear Engineering and Technology, 46(4), pp.547~556 (2014), 한국원자력학회
- "Dassault Systemes, SIMULIA User Assistance, Dassault Systems", Simulia Corp, ~ (2018)
