Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Arthur T. Motta; Aylin Yilmazbayhan; Marcelo J.Gomes da Silva; Robert J. Comstock; Gary S. Was; Jeremy T. Busby; Eric Gartner; Qunjia Peng; Yong Hwan Jeong; Jeong Yong Park

doi:10.1016/j.jnucmat.2007.05.022

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Arthur T. Motta, Aylin Yilmazbayhan, Marcelo J.Gomes da Silva, Robert J. Comstock, Gary S. Was, Jeremy T. Busby, Eric Gartner, Qunjia Peng, Yong Hwan Jeong, Jeong Yong Park

Research output: Contribution to journal › Article › peer-review

162 Scopus citations

Abstract

The corrosion behavior of model Zr-based alloys at 500 °C is assessed by long term (up to 400 days) corrosion testing in an effort to evaluate their potential for use in the supercritical water reactor and to assess the influence of alloying elements on corrosion behavior. The corrosion weight gains from such systematic testing are seen to be a factor of five higher than those measured at 360 °C but the protectiveness ranking of the alloys is similar. Detailed characterization of the oxide layers to rationalize the differences in corrosion behavior was performed using synchrotron radiation and systematic differences are observed in protective and non-protective oxides, especially near the oxide-metal interface. The overall corrosion rate of the best Zr-based alloys compared favorably with those of other alloys being considered for use in the supercritical water reactor.

Original language	English
Pages (from-to)	61-75
Number of pages	15
Journal	Journal of Nuclear Materials
Volume	371
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2007.05.022
State	Published - Sep 15 2007
Externally published	Yes

Funding

The authors would like to thank Z. Cai, Y. Chu, J. Ilavsky and B. Lai at Argonne National Laboratory for their assistance with the experiments at APS. This research was supported by a DOE I-NERI grant no. DE-FG07-03RL14530 and by MOST at KAERI. Use of the Advanced Photon Source was supported by the US Department of Energy, Basic Energy Sciences, Office of Science, under Contract No. W-31-109-Eng-38. M.J. Gomes da Silva was a recipient of a scholarship from CNPq-Brazil for his doctoral study, while working on this project.

Funders	Funder number
US Department of Energy
U.S. Department of Energy	DE-FG07-03RL14530
Office of Science
Basic Energy Sciences
Ministry of Science and Technology

Access to Document

10.1016/j.jnucmat.2007.05.022

Cite this

@article{41c4ff58c64a4a7094519e556a593dfd,

title = "Zirconium alloys for supercritical water reactor applications: Challenges and possibilities",

abstract = "The corrosion behavior of model Zr-based alloys at 500 °C is assessed by long term (up to 400 days) corrosion testing in an effort to evaluate their potential for use in the supercritical water reactor and to assess the influence of alloying elements on corrosion behavior. The corrosion weight gains from such systematic testing are seen to be a factor of five higher than those measured at 360 °C but the protectiveness ranking of the alloys is similar. Detailed characterization of the oxide layers to rationalize the differences in corrosion behavior was performed using synchrotron radiation and systematic differences are observed in protective and non-protective oxides, especially near the oxide-metal interface. The overall corrosion rate of the best Zr-based alloys compared favorably with those of other alloys being considered for use in the supercritical water reactor.",

author = "Motta, {Arthur T.} and Aylin Yilmazbayhan and {da Silva}, {Marcelo J.Gomes} and Comstock, {Robert J.} and Was, {Gary S.} and Busby, {Jeremy T.} and Eric Gartner and Qunjia Peng and Jeong, {Yong Hwan} and Park, {Jeong Yong}",

year = "2007",

month = sep,

day = "15",

doi = "10.1016/j.jnucmat.2007.05.022",

language = "English",

volume = "371",

pages = "61--75",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

number = "1-3",

}

TY - JOUR

T1 - Zirconium alloys for supercritical water reactor applications

T2 - Challenges and possibilities

AU - Motta, Arthur T.

AU - Yilmazbayhan, Aylin

AU - da Silva, Marcelo J.Gomes

AU - Comstock, Robert J.

AU - Was, Gary S.

AU - Busby, Jeremy T.

AU - Gartner, Eric

AU - Peng, Qunjia

AU - Jeong, Yong Hwan

AU - Park, Jeong Yong

PY - 2007/9/15

Y1 - 2007/9/15

N2 - The corrosion behavior of model Zr-based alloys at 500 °C is assessed by long term (up to 400 days) corrosion testing in an effort to evaluate their potential for use in the supercritical water reactor and to assess the influence of alloying elements on corrosion behavior. The corrosion weight gains from such systematic testing are seen to be a factor of five higher than those measured at 360 °C but the protectiveness ranking of the alloys is similar. Detailed characterization of the oxide layers to rationalize the differences in corrosion behavior was performed using synchrotron radiation and systematic differences are observed in protective and non-protective oxides, especially near the oxide-metal interface. The overall corrosion rate of the best Zr-based alloys compared favorably with those of other alloys being considered for use in the supercritical water reactor.

AB - The corrosion behavior of model Zr-based alloys at 500 °C is assessed by long term (up to 400 days) corrosion testing in an effort to evaluate their potential for use in the supercritical water reactor and to assess the influence of alloying elements on corrosion behavior. The corrosion weight gains from such systematic testing are seen to be a factor of five higher than those measured at 360 °C but the protectiveness ranking of the alloys is similar. Detailed characterization of the oxide layers to rationalize the differences in corrosion behavior was performed using synchrotron radiation and systematic differences are observed in protective and non-protective oxides, especially near the oxide-metal interface. The overall corrosion rate of the best Zr-based alloys compared favorably with those of other alloys being considered for use in the supercritical water reactor.

UR - http://www.scopus.com/inward/record.url?scp=34547837521&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2007.05.022

DO - 10.1016/j.jnucmat.2007.05.022

M3 - Article

AN - SCOPUS:34547837521

SN - 0022-3115

VL - 371

SP - 61

EP - 75

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3

ER -

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Abstract

Funding

Access to Document

Other files and links

Fingerprint

Cite this