Continuum model for hydrogen pickup in zirconium alloys of LWR fuel cladding

Wang, Xing; Zheng, Ming-Jie; Szlufarska, Izabela; Morgan, Dane

doi:10.1063/1.4979472

Title: Continuum model for hydrogen pickup in zirconium alloys of LWR fuel cladding

Journal Article · Mon Apr 03 00:00:00 EDT 2017 · Journal of Applied Physics

DOI:https://doi.org/10.1063/1.4979472· OSTI ID:1465333

Wang, Xing ^[1]; Zheng, Ming-Jie ^[2]; Szlufarska, Izabela ^[3];

^[3]

Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineering Physics and Nuclear Engineering
Univ. of Wisconsin, Madison, WI (United States). Dept. of Materials Science and Engineering; Chinese Academy of Sciences (CAS), Hefei (China). Key Lab. of Neutronics and Radiation Safety. Inst. of Nuclear Energy Safety Technology
Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineering Physics and Nuclear Engineering. Dept. of Materials Science and Engineering

A continuum model for calculating the time-dependent hydrogen pickup fractions in various Zirconium alloys under steam and pressured water oxidation has been developed in this paper. Using only one fitting parameter, the effective hydrogen gas partial pressure at the oxide surface, a qualitative agreement is obtained between the predicted and previously measured hydrogen pickup fractions. The calculation results therefore demonstrate that H diffusion through the dense oxide layer plays an important role in the hydrogen pickup process. Finally, the limitations and possible improvement of the model are also discussed.

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Research Organization:: Univ. of Wisconsin, Madison, WI (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725; FG02-08ER46493

OSTI ID:: 1465333

Alternate ID(s):: OSTI ID: 1361801

Journal Information:: Journal of Applied Physics, Vol. 121, Issue 13; ISSN 0021-8979

Publisher:: American Institute of Physics (AIP)Copyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 7 works

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References (39)

A hydrogen uptake micro-mechanism for Zr alloys Cox, B.; Wong, Y. -M Journal of Nuclear Materials, Vol. 270, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00898-8	journal	April 1999
Oxidation of Zirconium and Zirconium Alloys Porte, H. A.; Schnizlein, J. G.; Vogel, R. C. Journal of The Electrochemical Society, Vol. 107, Issue 6 https://doi.org/10.1149/1.2427733	journal	January 1960
Electrical Resistivity of Stabilized Zirconia at Elevated Temperatures Dixon, J. M.; LaGrange, L. D.; Merten, U. Journal of The Electrochemical Society, Vol. 110, Issue 4 https://doi.org/10.1149/1.2425731	journal	January 1963
Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics Couet, Adrien; Motta, Arthur T.; Comstock, Robert J. Journal of Nuclear Materials, Vol. 451, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.03.001	journal	August 2014
Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys Cox, B. Journal of Nuclear Materials, Vol. 336, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2004.09.029	journal	February 2005
Materials challenges in nuclear energy Zinkle, S. J.; Was, G. S. Acta Materialia, Vol. 61, Issue 3 https://doi.org/10.1016/j.actamat.2012.11.004	journal	February 2013
Kinetics of Hydrogen Absorption and Release in Zirconium Alloys During Steam Oxidation Grosse, M.; Steinbrueck, M.; Lehmann, E. Oxidation of Metals, Vol. 70, Issue 3-4 https://doi.org/10.1007/s11085-008-9113-2	journal	July 2008
The Cyclic Nature of Corrosion of Zr and Zr-Sn in High-Temperature Water (633 K) Schefold, J.; Lincot, D.; Ambard, A. Journal of The Electrochemical Society, Vol. 150, Issue 10 https://doi.org/10.1149/1.1602079	journal	January 2003
Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding Motta, Arthur T.; Couet, Adrien; Comstock, Robert J. Annual Review of Materials Research, Vol. 45, Issue 1 https://doi.org/10.1146/annurev-matsci-070214-020951	journal	July 2015
Diffusion of Hydrogen in the Oxides of Zr—1Nb, Zr—2.5Nb and Zr—20Nb Alloys* Khatamian, D. Zeitschrift für Physikalische Chemie, Vol. 181, Issue Part_1_2 https://doi.org/10.1524/zpch.1993.181.Part_1_2.435	journal	January 1993
An ion beam study of hydrogen diffusion in oxides of Zr and Zr-Nb (2.5 wt%) Khatamian, D.; Manchester, F. D. Journal of Nuclear Materials, Vol. 166, Issue 3 https://doi.org/10.1016/0022-3115(89)90226-2	journal	August 1989
Hydrogen diffusion in oxides formed on surfaces of zirconium alloys Khatamian, D. Journal of Alloys and Compounds, Vol. 253-254 https://doi.org/10.1016/S0925-8388(96)03068-X	journal	May 1997
The effect of alloying modifications on hydrogen uptake of zirconium-alloy welding specimens during corrosion tests Yao, M. Y.; Zhou, B. X.; Li, Q. Journal of Nuclear Materials, Vol. 350, Issue 2 https://doi.org/10.1016/j.jnucmat.2005.12.005	journal	April 2006
Corrosion of zirconium alloys in concentrated lithium hydroxide solutions Müller, S.; Lanzani, L. Journal of Nuclear Materials, Vol. 439, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.07.030	journal	August 2013
Role of Intermetallic Precipitates in Hydrogen Uptake of Zircaloy-2 Hatano, Yuji; Isobe, Kanetsugu; Hitaka, Ryuji Journal of Nuclear Science and Technology, Vol. 33, Issue 12 https://doi.org/10.1080/18811248.1996.9732036	journal	December 1996
Deuterium diffusion in oxide layers of Zr–2.5Nb alloy Une, K.; Sakamoto, K.; Takagi, I. Journal of Nuclear Materials, Vol. 439, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.04.003	journal	August 2013
Strain effects on oxygen transport in tetragonal zirconium dioxide Bai, Xian-Ming; Zhang, Yongfeng; Tonks, Michael R. Physical Chemistry Chemical Physics, Vol. 15, Issue 44 https://doi.org/10.1039/c3cp53562b	journal	January 2013
Porosity in oxides on zirconium fuel cladding alloys, and its importance in controlling oxidation rates Ni, N.; Lozano-Perez, S.; Jenkins, M. L. Scripta Materialia, Vol. 62, Issue 8 https://doi.org/10.1016/j.scriptamat.2009.12.043	journal	April 2010
SIMS studies of hydrogen diffusion through oxides on ZrNb alloy McIntyre, N. S.; Davidson, R. D.; Weisener, C. G. Surface and Interface Analysis, Vol. 17, Issue 11 https://doi.org/10.1002/sia.740171102	journal	October 1991
Tritium release from Zircaloy-2: Dependence on temperature, surface conditions and composition of surrounding medium Kunz, Willfried; Münzel, Helmut; Kunz, Ulrike Journal of Nuclear Materials, Vol. 136, Issue 1 https://doi.org/10.1016/0022-3115(85)90026-1	journal	October 1985
Properties of zirconium base cladding materials-corrosion and hydrogen pickup Videm, Ketil Nuclear Engineering and Design, Vol. 21, Issue 2 https://doi.org/10.1016/0029-5493(72)90073-8	journal	January 1972
Modelling of hydrogen absorption by zirconium alloys during high temperature oxidation in steam Veshchunov, M. S.; Berdyshev, A. V. Journal of Nuclear Materials, Vol. 255, Issue 2-3 https://doi.org/10.1016/S0022-3115(98)00018-X	journal	June 1998
Tritium diffusion in zircaloy-2 in the temperature range −78 to 204° C Austin, J. H.; Elleman, T. S.; Verghese, K. Journal of Nuclear Materials, Vol. 51, Issue 3 https://doi.org/10.1016/0022-3115(74)90197-4	journal	July 1974
Deuterium diffusion in steam-corroded oxide layer of zirconium alloys Takagi, I.; Une, K.; Miyamura, S. Journal of Nuclear Materials, Vol. 419, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.06.001	journal	December 2011
Deuterium diffusion in LiOH–water-corroded oxide layer of zirconium alloys Une, K.; Takagi, I.; Sawada, K. Progress in Nuclear Energy, Vol. 57 https://doi.org/10.1016/j.pnucene.2011.11.009	journal	May 2012
Hydrogen uptake during oxidation of zirconium alloys Cox, B. Journal of Alloys and Compounds, Vol. 256, Issue 1-2 https://doi.org/10.1016/S0925-8388(96)02852-6	journal	July 1997
How the crystallography and nanoscale chemistry of the metal/oxide interface develops during the aqueous oxidation of zirconium cladding alloys Ni, N.; Hudson, D.; Wei, J. Acta Materialia, Vol. 60, Issue 20 https://doi.org/10.1016/j.actamat.2012.09.021	journal	December 2012
Oxidation and hydrogen uptake in zirconium, Zircaloy-2 and Zircaloy-4: Computational thermodynamics and ab initio calculations Glazoff, Michael V.; Tokuhiro, Akira; Rashkeev, Sergey N. Journal of Nuclear Materials, Vol. 444, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.038	journal	January 2014
Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate Yilmazbayhan, Aylin; Motta, Arthur T.; Comstock, Robert J. Journal of Nuclear Materials, Vol. 324, Issue 1 https://doi.org/10.1016/j.jnucmat.2003.08.038	journal	January 2004
Effect of surface strain on oxygen adsorption on Zr (0001) surface Wang, X.; Khafizov, M.; Szlufarska, I. Journal of Nuclear Materials, Vol. 445, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.046	journal	February 2014
Hydrogen Dissolution in and Release from Nonmetals: III, Tetragonal Zirconia Park, Kwangheon; Olander, Donald R. Journal of the American Ceramic Society, Vol. 74, Issue 1 https://doi.org/10.1111/j.1151-2916.1991.tb07299.x	journal	January 1991
A mechanism for the hydrogen uptake process in zirconium alloys Cox, B. Journal of Nuclear Materials, Vol. 264, Issue 3 https://doi.org/10.1016/S0022-3115(98)00492-9	journal	January 1999
New insight into crack formation during corrosion of zirconium-based metal-oxide systems Vermaak, Natasha; Parry, Guillaume; Estevez, Rafael Acta Materialia, Vol. 61, Issue 12 https://doi.org/10.1016/j.actamat.2013.04.009	journal	July 2013
Hydride Formation in Zirconium Alloys Motta, Arthur T.; Chen, Long-Qing JOM, Vol. 64, Issue 12 https://doi.org/10.1007/s11837-012-0479-x	journal	October 2012
Transport mechanism of hydrogen through oxide film formed on zircaloy-4 Hatano, Y.; Hitaka, R.; Sugisaki, M. Journal of Radioanalytical and Nuclear Chemistry, Vol. 239, Issue 3 https://doi.org/10.1007/BF02349048	journal	March 1999
In-situ neutron radiography investigations of hydrogen diffusion and absorption in zirconium alloys Grosse, M.; van den Berg, M.; Goulet, C. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 651, Issue 1 https://doi.org/10.1016/j.nima.2010.12.070	journal	September 2011
Ab initio study of hydrogen diffusion in zirconium oxide Muta, Hiroaki; Etoh, Yoshinori; Ohishi, Yuji Journal of Nuclear Science and Technology, Vol. 49, Issue 5 https://doi.org/10.1080/00223131.2012.676820	journal	May 2012
Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO™ oxide layers de Gabory, Benoit; Motta, Arthur T.; Wang, Ke Journal of Nuclear Materials, Vol. 456 https://doi.org/10.1016/j.jnucmat.2014.09.073	journal	January 2015
Oxidation of Zirconium and Zirconium Alloys Porte, H. A.; Schnizlein, J. G.; Vogel, R. C. https://doi.org/10.2172/4221424	report	September 1959

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