Three-dimensional numerical simulation of hydrogen-induced multi-field coupling behavior in cracked zircaloy cladding tubes |
Xia, Zhongjia
(Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan University)
Wang, Bingzhong (Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan University) Zhang, Jingyu (Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan University) Ding, Shurong (Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan University) Chen, Liang (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institution of China) Pang, Hua (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institution of China) Song, Xiaoming (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institution of China) |
1 | X.H. Guo, S.Q. Shi, Q.M. Zhang, et al., An elastoplastic phase-field model for the evolution of hydride precipitation in zirconium. Part II: specimen with flaws, J. Nucl. Mater. 378 (1) (2008) 120-125. DOI |
2 | X. Gong, Y. Zhao, S. Ding, A new method to simulate the micro-thermomechanical behaviors evolution in dispersion nuclear fuel elements, Mech. Mater. 77 (2014) 14-27. DOI |
3 | M.P. Puls, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking, Springer Science & Business Media, 2012. |
4 | Jingyu Zhang, et al., A theoretical model for delayed hydride cracking velocity considering the temperature history and temperature gradients, Nucl. Mater. Energy 16 (2018) 95-107. DOI |
5 | K.S. Chan, A micromechanical model for predicting hydride embrittlement in nuclear fuel cladding material, J. Nucl. Mater. 227 (3) (1996) 220-236. DOI |
6 | K. Une, S. Ishimoto, Y. Etoh, et al., The terminal solid solubility of hydrogen in irradiated Zircaloy-2 and microscopic modeling of hydride behavior, J. Nucl. Mater. 389 (1) (2009) 127-136. DOI |
7 | A.T. Motta, L.Q. Chen, Hydride formation in zirconium alloys, JOM (J. Occup. Med.) 64 (12) (2012) 1403-1408. |
8 | J.A. Szpunar, W. Qin, H. Li, et al., Roles of texture in controlling oxidation, hydrogen ingress and hydride formation in Zr alloys, J. Nucl. Mater. 427 (1) (2012) 343-349. DOI |
9 | C. Sun, J. Tan, et al., Critical temperature of delayed hydride cracking in N-18 Zircaloy, Acta Metall. Sin. 45 (5) (2009) 541-546. DOI |
10 | W.J. Zhao, Development of new nuclear cladding in French PWR, Nucl. Power Eng. 21 (3) (2000) 278-284. DOI |
11 | Y. Gou, Y. Li, Y. Liu, et al., Evaluation of a delayed hydride cracking in Zr-2.5 Nb CANDU and RBMK pressure tubes, Mater. Des. 30 (4) (2009) 1231-1235. DOI |
12 | M.D. Pandey, M. Wang, G.A. Bickel, A probabilistic approach to update lower bound threshold stress intensity factor (K IH) for delayed hydride cracking, Nucl. Eng. Des. 240 (10) (2010) 2682-2690. DOI |
13 | A. Zielinski, S. Sobieszczyk, Hydrogen-enhanced degradation and oxide effects in zirconium alloys for nuclear applications, Int. J. Hydrogen Energy 36 (14) (2011) 8619-8629. DOI |
14 | A.M. Garde, G.P. Smith, R.C. Pirek, Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4//Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM International, 1996. |
15 | M.D. Pandey, D.D. Radford, A statistical approach to the prediction of pressure tube fracture toughness, Nucl. Eng. Des. 238 (12) (2008) 3218-3226. DOI |
16 | J.I. Mieza, G.L. Vigna, G. Domizzi, Evaluation of variables affecting crack propagation by Delayed Hydride Cracking in Zr-2.5 Nb with different heat treatments, J. Nucl. Mater. 411 (1) (2011) 150-159. DOI |
17 | L.O. Jernkvist, Multi-field modelling of hydride forming metals Part I: model formation and validation, Comput. Mater. Sci. 85 (2014) 383-401. DOI |
18 | N. Hashimoto, T.S. Byun, K. Farrell, et al., Deformation microstructure of neutron-irradiated pure polycrystalline metals, J. Nucl. Mater. 329 (2004) 947-952. DOI |
19 | E.R. Bradley, G.P. Sabol, Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM, 1996. |
20 | F. Yunchang, D.A. Koss, The influence of multiaxial states of stress on the hydrogen embrittlement of zirconium alloy sheet, Metall. Trans. A 16 (4) (1985) 675-681. DOI |
21 | J.H. Huang, S.P. Huang, Effect of hydrogen contents on the mechanical properties of Zircaloy-4, J. Nucl. Mater. 208 (1) (1994) 166-179. DOI |
22 | G.P. Marino, HYDIZ, A 2-dimensonal computer program for migration of interstitial solutes of finite solubility in a thermal gradient (LWBR Development Program), Bettis Atomic Power Lab., Pittsburgh, PA (USA), 1974. |
23 | J. Freund, A Model for Thermal Diffusion of Hydrogen in Zirconium Alloys, Helsinki University of Technology, 1992. |
24 | A.G. Varias, A.R. Massih, Hydride-induced embrittlement and fracture in metalsdeffect of stress and temperature distribution, J. Mech. Phys. Solid. 50 (7) (2002) 1469-1510. DOI |
25 | P. Sofronis, R.M. McMeeking, Numerical analysis of hydrogen transport near a blunting crack tip, J. Mech. Phys. Solid. 37 (3) (1989) 317-350. DOI |
26 | L.J. Siefken, E.W. Coryell, E.A. Harvego, et al., MATPRO-A Library of Materials Properties for Light-water-reactor Accident Analysis. Idaho Falls, Idaho National Engineering and Environmental Laboratory, 2001. |
27 | D.R. Metzger, R.G. Sauve, A Self-induced Stress Model for Simulating Hydride Formation at Flaws, American Society of Mechanical Engineers, New York, NY (United States), 1996. |
28 | J. Lufrano, P. Sofronis, Micromechanics of hydride formation and cracking in zirconium alloys, Comput. Model. Eng. Sci. 1 (2) (2000) 119-131. |
29 | J. Lufrano, P. Sofronis, H.K. Birnbaum, Elastoplastically accommodated hydride formation and embrittlement, J. Mech. Phys. Solid. 46 (9) (1998) 1497-1520. DOI |
30 | J. Lufrano, P. Sofronis, H.K. Birnbaum, Modeling of hydrogen transport and elastically accommodated hydride formation near a crack tip, J. Mech. Phys. Solid. 44 (2) (1996) 179-205. DOI |
31 | A.G. Varias, A.R. Massih, Simulation of hydrogen embrittlement in zirconium alloys under stress and temperature gradients, J. Nucl. Mater. 279 (2) (2000) 273-285. DOI |
32 | A.G. Varias, J.L. Feng, Simulation of hydride-induced steady-state crack growth in metals-Part I: growth near hydrogen chemical equilibrium, Comput. Mech. 34 (5) (2004) 339-356. DOI |
33 |
X.Q. Ma, S.Q. Shi, C.H. Woo, et al., The phase field model for hydrogen diffusion and |
34 | M.P. Puls, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking, Springer Science & Business Media, 2012. |
35 | X.H. Guo, S.Q. Shi, Q.M. Zhang, et al., An elastoplastic phase-field model for the evolution of hydride precipitation in zirconium. Part I: smooth specimen, J. Nucl. Mater. 378 (1) (2008) 110-119. DOI |
36 | P. Shewmon, Diffusion in Solids. The Minerals, Metals & Materials Society, Diffusion in Solids, second ed., Retroactive Coverage, United States), 1989, p. 246, 1989. |
37 |
C.E. Coleman, D. Hardie, The hydrogen embrittlement of |
38 | L.O. Jernkvist, A.R. Massih, Multi-field modelling of hydride forming metals. Part I: model formulation and validation, Comput. Mater. Sci. 85 (2014) 363-382. DOI |
39 | C.E. Coleman, Cracking of hydride-forming metals and alloys, in: Comprehensive Structural Integrity, 6, 2003, pp. 103-161. |
40 | C.K. Chao, K.C. Yang, C.C. Tseng, Rupture of spent fuel Zircaloy cladding in dry storage due to delayed hydride cracking, Nucl. Eng. Des. 238 (1) (2008) 124-129. DOI |
41 | C.L. Briant, Z.F. Wang, N. Chollocoop, Hydrogen embrittlement of commercial purity titanium, Corrosion Sci. 44 (8) (2002) 1875-1888. DOI |
42 | A.G. Varias, J.L. Feng, Simulation of hydride-induced steady-state crack growth in metalsePart I: growth near hydrogen chemical equilibrium, Comput. Mech. 34 (5) (2004) 339-356. DOI |
43 | S.Q. Shi, M.P. Puls, Dependence of the threshold stress intensity factor on hydrogen concentration during delayed hydride cracking in zirconium alloys, J. Nucl. Mater. 218 (1) (1995) 30-36. DOI |
44 | E. Smith, Threshold stress criterion for delayed hydride crack initiation at a blunt notch in zirconium alloys, Int. J. Pres. Ves. Pip. 68 (1) (1996) 53-61. DOI |
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