Dissolution of Intermetallic Second-Phase Particles in Zircaloy-2 in High-Temperature Steam

doi:https://doi.org/10.1007/s11661-018-5090-5

Title: Dissolution of Intermetallic Second-Phase Particles in Zircaloy-2 in High-Temperature Steam

Abstract

The stability of intermetallic second-phase particles (SPPs) in coated Zircaloy-2 was studied in 700 °C steam environments up to 20 hours. Hydrogen generated from high-temperature steam oxidation of uncoated Zr-induced δ-hydrides formation in the Zircaloy matrix. Synchrotron XRD demonstrated that longer exposure times increased hydride peak intensity and decreased intermetallic SPPs’ peak intensity. Cross-sectional SEM analysis verified the intermetallic SPPs’ volume fraction reduction. The size distribution of intermetallic SPPs was characterized and larger particles were dissolved at longer oxidation time. Finally, a correlation between the hydrogen concentration and the volume fraction of intermetallic SPPs at 700 °C steam environment was found, with the volume fraction of SPPs decreasing as hydrogen concentration increases.

Authors:

Zhong, Weicheng ^[1]; Liu, Xiang ^[1]; Mouche, Peter A. ^[1]; Lin, Jun-Li ^[1]; Park, Donghee ^[1]; Elbakhshwan, Mohamed S. ^[2]; Gill, Simerjeet K. ^[3]; Ren, Yang ^[4]; Stubbins, James F. ^[1]; Heuser, Brent J. ^[1]

Univ. of Illinois, Urbana, IL (United States). Dept. of Nuclear, Plasma, and Radiological Engineering
Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineering Physics
Brookhaven National Lab. (BNL), Upton, NY (United States). Nuclear Science and Technology Dept.
Argonne National Lab. (ANL), Argonne, IL (United States). X-ray Science Division

Publication Date:: 2019-01-10

Research Org.:: Brookhaven National Lab. (BNL), Upton, NY (United States); Argonne National Lab. (ANL), Argonne, IL (United States); Univ. of Illinois at Urbana-Champaign, IL (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Nuclear Physics (NP) (SC-26); USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22). Scientific User Facilities Division; USDOE Office of Nuclear Energy (NE), Nuclear Energy University Programs (NEUP); USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22). Materials Sciences & Engineering Division

OSTI Identifier:: 1503231

Alternate Identifier(s):: OSTI ID: 1524420; OSTI ID: 1607437

Report Number(s):: BNL-211453-2019-JAAM
Journal ID: ISSN 1073-5623

Grant/Contract Number:: SC0012704; FG02-07ER46471; FG02-07ER46453; AC02-06CH11357

Resource Type:: Journal Article: Accepted Manuscript

Journal Name:: Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science

Additional Journal Information:: Journal Volume: 50; Journal Issue: 4; Journal ID: ISSN 1073-5623

Publisher:: ASM International

Country of Publication:: United States

Language:: English

Subject:: 73 NUCLEAR PHYSICS AND RADIATION PHYSICS

Citation Formats


                    Zhong, Weicheng, Liu, Xiang, Mouche, Peter A., Lin, Jun-Li, Park, Donghee, Elbakhshwan, Mohamed S., Gill, Simerjeet K., Ren, Yang, Stubbins, James F., and Heuser, Brent J. Dissolution of Intermetallic Second-Phase Particles in Zircaloy-2 in High-Temperature Steam.  United States: N. p., 2019. 
        Web.  doi:10.1007/s11661-018-5090-5.

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                    Zhong, Weicheng, Liu, Xiang, Mouche, Peter A., Lin, Jun-Li, Park, Donghee, Elbakhshwan, Mohamed S., Gill, Simerjeet K., Ren, Yang, Stubbins, James F., & Heuser, Brent J. Dissolution of Intermetallic Second-Phase Particles in Zircaloy-2 in High-Temperature Steam.  United States.  https://doi.org/10.1007/s11661-018-5090-5

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                    Zhong, Weicheng, Liu, Xiang, Mouche, Peter A., Lin, Jun-Li, Park, Donghee, Elbakhshwan, Mohamed S., Gill, Simerjeet K., Ren, Yang, Stubbins, James F., and Heuser, Brent J. Thu .  
        "Dissolution of Intermetallic Second-Phase Particles in Zircaloy-2 in High-Temperature Steam".  United States.  https://doi.org/10.1007/s11661-018-5090-5.  https://www.osti.gov/servlets/purl/1503231.

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@article{osti_1503231,

  title        = {Dissolution of Intermetallic Second-Phase Particles in Zircaloy-2 in High-Temperature Steam},

  author       = {Zhong, Weicheng and Liu, Xiang and Mouche, Peter A. and Lin, Jun-Li and Park, Donghee and Elbakhshwan, Mohamed S. and Gill, Simerjeet K. and Ren, Yang and Stubbins, James F. and Heuser, Brent J.},

  abstractNote = {The stability of intermetallic second-phase particles (SPPs) in coated Zircaloy-2 was studied in 700 °C steam environments up to 20 hours. Hydrogen generated from high-temperature steam oxidation of uncoated Zr-induced δ-hydrides formation in the Zircaloy matrix. Synchrotron XRD demonstrated that longer exposure times increased hydride peak intensity and decreased intermetallic SPPs’ peak intensity. Cross-sectional SEM analysis verified the intermetallic SPPs’ volume fraction reduction. The size distribution of intermetallic SPPs was characterized and larger particles were dissolved at longer oxidation time. Finally, a correlation between the hydrogen concentration and the volume fraction of intermetallic SPPs at 700 °C steam environment was found, with the volume fraction of SPPs decreasing as hydrogen concentration increases.},

  doi          = {10.1007/s11661-018-5090-5},

  url          = {https://www.osti.gov/biblio/1503231},
  journal      = {Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science},

  issn         = {1073-5623},

  number       = 4,

  volume       = 50,

  place        = {United States},

  year         = {2019},

  month        = {1}

}

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Works referenced in this record:

The stability of alloying additions in Zirconium
journal, June 2013

Lumley, S. C.; Murphy, S. T.; Burr, P. A.
Journal of Nuclear Materials, Vol. 437, Issue 1-3
https://doi.org/10.1016/j.jnucmat.2013.01.335

A ballistic mixing model for the amorphization of precipitates in Zircaloy under neutron irradiation
journal, November 1992

Motta, Arthur T.; Lemaignan, Clément
Journal of Nuclear Materials, Vol. 195, Issue 3
https://doi.org/10.1016/0022-3115(92)90519-Q

Characterization of single crystal uranium-oxide thin films grown via reactive-gas magnetron sputtering on yttria-stabilized zirconia and sapphire
journal, June 2012

Strehle, Melissa M.; Heuser, Brent J.; Elbakhshwan, Mohamed S.
Thin Solid Films, Vol. 520, Issue 17
https://doi.org/10.1016/j.tsf.2012.04.022

Evaluating zirconium–zirconium hydride interfacial strains by nano-beam electron diffraction
journal, January 2013

Barrow, A. T. W.; Korinek, A.; Daymond, M. R.
Journal of Nuclear Materials, Vol. 432, Issue 1-3
https://doi.org/10.1016/j.jnucmat.2012.08.003

An in situ neutron diffraction study of the thermal disproportionation of the Zr2FeD5 system
journal, May 2011

Pitt, M. P.; Pitt, L. K. W.; Fjellvåg, H.
Journal of Alloys and Compounds, Vol. 509, Issue 18
https://doi.org/10.1016/j.jallcom.2011.02.129

Study of the mechanical behavior of the hydride blister/rim structure in Zircaloy-4 using in-situ synchrotron X-ray diffraction
journal, April 2016

Lin, Jun-li; Han, Xiaochun; Heuser, Brent J.
Journal of Nuclear Materials, Vol. 471
https://doi.org/10.1016/j.jnucmat.2015.12.048

Response of Cr and Cr-Al coatings on Zircaloy-2 to high temperature steam
journal, January 2018

Zhong, Weicheng; Mouche, Peter A.; Heuser, Brent J.
Journal of Nuclear Materials, Vol. 498
https://doi.org/10.1016/j.jnucmat.2017.10.021

Diffusion coefficient of hydrogen in alpha zirconium, Zircaloy-2 and Zircaloy-4
journal, June 1972

Kearns, J. J.
Journal of Nuclear Materials, Vol. 43, Issue 3
https://doi.org/10.1016/0022-3115(72)90065-7

An oxide-semiconductance model of nodular corrosion and its application to Zirconium alloy development
journal, August 1991

Taylor, D. F.
Journal of Nuclear Materials, Vol. 184, Issue 1
https://doi.org/10.1016/0022-3115(91)90534-E

Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction
journal, August 2009

Daum, R. S.; Chu, Y. S.; Motta, A. T.
Journal of Nuclear Materials, Vol. 392, Issue 3
https://doi.org/10.1016/j.jnucmat.2009.04.004

Study of secondary intermetallic phase precipitation/dissolution in Zr alloys by high temperature–high sensitivity calorimetry
journal, January 2008

Toffolon-Masclet, C.; Guilbert, T.; Brachet, J. C.
Journal of Nuclear Materials, Vol. 372, Issue 2-3
https://doi.org/10.1016/j.jnucmat.2007.04.042

The dilatational misfit of zirconium hydrides precipitated in zirconium
journal, October 1973

Carpenter, G. J. C.
Journal of Nuclear Materials, Vol. 48, Issue 3
https://doi.org/10.1016/0022-3115(73)90022-6

Role of Intermetallic Precipitates in Hydrogen Uptake of Zircaloy-2
journal, December 1996

Hatano, Yuji; Isobe, Kanetsugu; Hitaka, Ryuji
Journal of Nuclear Science and Technology, Vol. 33, Issue 12
https://doi.org/10.1080/18811248.1996.9732036

Morphology and composition of second phase particles in zircaloy-2
journal, January 1983

Chemelle, P.; Knorr, D. B.; Van Der Sande, J. B.
Journal of Nuclear Materials, Vol. 113, Issue 1
https://doi.org/10.1016/0022-3115(83)90166-6

Azimuthally anisotropic hydride lens structures in Zircaloy 4 nuclear fuel cladding: High-resolution neutron radiography imaging and BISON finite element analysis
journal, December 2017

Lin, Jun-Li; Zhong, Weicheng; Bilheux, Hassina Z.
Journal of Nuclear Materials, Vol. 496
https://doi.org/10.1016/j.jnucmat.2017.09.025

Second phase particles in Zircaloy-2
journal, October 1989

Meng, Xianying; Northwood, Derek O.
Journal of Nuclear Materials, Vol. 168, Issue 1-2
https://doi.org/10.1016/0022-3115(89)90573-4

Performance of iron–chromium–aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions
journal, March 2016

Zhong, Weicheng; Mouche, Peter A.; Han, Xiaochun
Journal of Nuclear Materials, Vol. 470
https://doi.org/10.1016/j.jnucmat.2015.11.037

Pressure dependence of hydrogen-induced transformations in C15 Laves phase DyFe2 studied by pressure differential scanning calorimetry
journal, February 2005

Li, H. -W.; Ishikawa, K.; Aoki, K.
Journal of Alloys and Compounds, Vol. 388, Issue 1
https://doi.org/10.1016/j.jallcom.2004.06.072

ZIRLO™ — An Alloy Development Success
journal, January 2005

Sabol, Gp
Journal of ASTM International, Vol. 2, Issue 2
https://doi.org/10.1520/JAI12942

In situ powder synchrotron and neutron diffraction study of Zr2Ni deuterides
journal, May 2005

Sørby, M. H.; Fjellvåg, H.; Hauback, B. C.
Journal of Alloys and Compounds, Vol. 394, Issue 1-2
https://doi.org/10.1016/j.jallcom.2004.11.001

Hydrogen accommodation in Zr second phase particles: Implications for H pick-up and hydriding of Zircaloy-2 and Zircaloy-4
journal, April 2013

Burr, P. A.; Murphy, S. T.; Lumley, S. C.
Corrosion Science, Vol. 69
https://doi.org/10.1016/j.corsci.2012.11.036

Factors controlling hydrogen-induced amorphization of C15 Laves compounds
journal, July 1992

Aoki, K.; Li, X-G.; Masumoto, T.
Acta Metallurgica et Materialia, Vol. 40, Issue 7
https://doi.org/10.1016/0956-7151(92)90115-U

Study on the Role of Second Phase Particles in Hydrogen Uptake Behavior of Zirconium Alloys
journal, January 2011

Yao, M. Y.; Wang, J. H.; Peng, J. C.
Journal of ASTM International, Vol. 8, Issue 2
https://doi.org/10.1520/JAI102948

Resistance to hydride formation in zirconium: An emerging possibility
journal, October 2006

Manikrishna, K.; Sain, A.; Samajdar, I.
Acta Materialia, Vol. 54, Issue 18
https://doi.org/10.1016/j.actamat.2006.06.004

Hydrogen Solubility and Microstructural Changes in Zircaloy-4 Due to Neutron Irradiation
journal, January 2011

Vizcaíno, P.; Flores, A. V.; Bozzano, P. B.
Journal of ASTM International, Vol. 8, Issue 1
https://doi.org/10.1520/JAI102949

Phase Transformation Temperatures and Solute Redistribution in a Quaternary Zirconium Alloy
journal, May 2018

Cochrane, C.; Daymond, M. R.
Metallurgical and Materials Transactions A, Vol. 49, Issue 8
https://doi.org/10.1007/s11661-018-4662-8

Crystallography of Zirconium Hydrides in Recrystallized Zircaloy-2 Fuel Cladding by Electron Backscatter Diffraction
journal, July 2004

Une, Katsumi; Nogita, Kazuhiro; Ishimoto, Shinji
Journal of Nuclear Science and Technology, Vol. 41, Issue 7
https://doi.org/10.1080/18811248.2004.9715540

Phase instability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation
journal, September 1987

Griffiths, M.; Gilbert, R. W.; Carpenter, G. J. C.
Journal of Nuclear Materials, Vol. 150, Issue 1
https://doi.org/10.1016/0022-3115(87)90093-6

Phase separation in hydrides of Zr2Ni
journal, July 1990

Aubertin, F.; Campbell, S. J.
Hyperfine Interactions, Vol. 54, Issue 1-4
https://doi.org/10.1007/BF02396126

Zr2FeHx system hydrided at low temperatures: structural aspects by Mössbauer and x-ray diffraction studies
journal, February 1992

Raj, P.; Suryanarayana, P.; Sathyamoorthy, A.
Journal of Alloys and Compounds, Vol. 178, Issue 1-2
https://doi.org/10.1016/0925-8388(92)90280-M

Hydrogen-induced amorphization in the C14 Laves compound NdMn ₂
journal, April 2004

Ishikawa, K.; Ogasawara, N.; Aoki, K.
Philosophical Magazine Letters, Vol. 84, Issue 4
https://doi.org/10.1080/09500830410001663725

Effects of microchemistry and precipitate size on nodular corrosion resistance of Zircaloy-2
journal, July 1992

Kruger, R. M.; Adamson, R. B.; Brenner, S. S.
Journal of Nuclear Materials, Vol. 189, Issue 2
https://doi.org/10.1016/0022-3115(92)90532-P

X-ray and time differential perturbed angular correlation measurements in ZrCr2 and ZrCr2H3 Laves phase compounds
journal, June 1995

Mestnik Filho, J.; Carbonari, A. W.; Pendl, W.
Journal of Alloys and Compounds, Vol. 224, Issue 1
https://doi.org/10.1016/0925-8388(95)01513-2

Effects of Fe and Cr on corrosion behavior of ZrFeCr alloys in 500°C steam
journal, February 2011

Wang, Jun; Fan, Hongyuan; Xiong, Ji
Nuclear Engineering and Design, Vol. 241, Issue 2
https://doi.org/10.1016/j.nucengdes.2010.11.014

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Similar Records

Title: Dissolution of Intermetallic Second-Phase Particles in Zircaloy-2 in High-Temperature Steam

Abstract

Citation Formats

The stability of alloying additions in Zirconium journal, June 2013

A ballistic mixing model for the amorphization of precipitates in Zircaloy under neutron irradiation journal, November 1992

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Evaluating zirconium–zirconium hydride interfacial strains by nano-beam electron diffraction journal, January 2013

An in situ neutron diffraction study of the thermal disproportionation of the Zr2FeD5 system journal, May 2011

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An oxide-semiconductance model of nodular corrosion and its application to Zirconium alloy development journal, August 1991

Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction journal, August 2009

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The dilatational misfit of zirconium hydrides precipitated in zirconium journal, October 1973

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Performance of iron–chromium–aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions journal, March 2016

Pressure dependence of hydrogen-induced transformations in C15 Laves phase DyFe2 studied by pressure differential scanning calorimetry journal, February 2005

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Phase instability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation journal, September 1987

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Zr2FeHx system hydrided at low temperatures: structural aspects by Mössbauer and x-ray diffraction studies journal, February 1992

Hydrogen-induced amorphization in the C14 Laves compound NdMn 2 journal, April 2004

Effects of microchemistry and precipitate size on nodular corrosion resistance of Zircaloy-2 journal, July 1992

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A ballistic mixing model for the amorphization of precipitates in Zircaloy under neutron irradiation
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Study of the mechanical behavior of the hydride blister/rim structure in Zircaloy-4 using in-situ synchrotron X-ray diffraction
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