The role of hydrogen in zirconium alloy corrosion

Ensor, B.; Lucente, A. M.; Frederick, M. J.; Sutliff, J.; Motta, A. T.

doi:10.1016/j.jnucmat.2017.08.046

Title: The role of hydrogen in zirconium alloy corrosion

Full Record
Other Related Research

Authors:: Ensor, B.; Lucente, A. M.; Frederick, M. J.; Sutliff, J.; Motta, A. T.

Publication Date:: 2017-12-01

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA), Office of Naval Reactors

OSTI Identifier:: 1549256

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Name: Journal of Nuclear Materials Journal Volume: 496 Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: Netherlands

Language:: English

Citation Formats


                    Ensor, B., Lucente, A. M., Frederick, M. J., Sutliff, J., and Motta, A. T. The role of hydrogen in zirconium alloy corrosion.  Netherlands: N. p., 2017. 
Web.  doi:10.1016/j.jnucmat.2017.08.046.

Copy to clipboard


                    Ensor, B., Lucente, A. M., Frederick, M. J., Sutliff, J., & Motta, A. T. The role of hydrogen in zirconium alloy corrosion.  Netherlands.  https://doi.org/10.1016/j.jnucmat.2017.08.046

Copy to clipboard


                    Ensor, B., Lucente, A. M., Frederick, M. J., Sutliff, J., and Motta, A. T. Fri .  
"The role of hydrogen in zirconium alloy corrosion".  Netherlands.  https://doi.org/10.1016/j.jnucmat.2017.08.046.

Copy to clipboard


                    
@article{osti_1549256,

  title        = {The role of hydrogen in zirconium alloy corrosion},

  author       = {Ensor, B. and Lucente, A. M. and Frederick, M. J. and Sutliff, J. and Motta, A. T.},

  abstractNote = {},

  doi          = {10.1016/j.jnucmat.2017.08.046},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 496,

  place        = {Netherlands},

  year         = {2017},

  month        = {12}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Publisher's Version of Record
https://doi.org/10.1016/j.jnucmat.2017.08.046

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 9 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Detrimental role of hydrogen on the corrosion rate of zirconium alloys

Conference Blat, M ; Noel, D

Recent studies have suggested that hydride precipitation at the metal/oxide interface could play a detrimental role on the waterside corrosion rate. Nevertheless, the mechanism of that detrimental role is not completely understood, and two hypotheses were investigated to understand the mechanism that controls the role of the hydrides. The first hypothesis is based on a mechanical effect: the hydrides precipitate at the metal/oxide interface and destroy the physical integrity of the barrier oxide layer. The second hypothesis is a modification of the transport properties of the oxide grown on the hydrided metal. The detrimental role of hydrides on the corrosionmore »« less
Understanding corrosion and hydrogen pickup of zirconium fuel cladding alloys: The role of oxide microstructure, porosity, sub-oxides, and second-phase particles - 2016-0071

Conference Hu, Jing ; Setiadinata, Brian ; Aarholt, Thomas ; ...

We used a range of advanced microscopy techniques to study the microstructure, nanoscale chemistry, and porosity in zirconium alloys at different stages of oxidation. Samples from both autoclave and in-reactor conditions were available, including ZIRLO{sup TM}, Zr-1.0Nb, and Zr-2.5Nb samples with different heat treatments. Scanning transmission electron microscopy (STEM), transmission Kikuchi diffraction (TKD), and automated crystal orientation mapping with TEM were used to study the grain structure and phase distribution. Significant differences in grain morphology were observed between samples oxidized in the autoclave and in-reactor, with shorter, less well-aligned monoclinic grains and more tetragonal grains in the neutron-irradiated samples. Amore »« less
https://doi.org/10.1520/STP159720160071
THE CORROSION OF ZIRCONIUM AND ITS ALLOYS IN HIGH TEMPERATURE STEAM. PART II. THE UPTAKE OF HYDROGEN DURING CORROSION

Technical Report Wanklyn, J N ; Silvester, D R ; Dalton, J ; ...

Determinations were made of the uptake of hydrogen by zirconium and a number of its alloys during corrosion by steam at 400 to 600 deg C. With some alloys, the instantaneous percentage uptake increases during corrosion, reaching nearly 100%. Several of the additions which confer corrosion resistance to high- temperature steam lead to high hydrogen uptakes. A ternary copper --tungsten alloy shows low uptakes, at least at 500 deg C and above. Binary iron alloys also appear promising. The mechanism of hydrogen entry is discussed. (auth)
Hydrogen Uptake of Zirconium Alloys During Water and Steam Corrosion

Journal Article KLEPFER, H. H. - Corrosion (Houston)

Corrosion H weight gains were studied for four Zr-base binary systems: Zr--Fe, Zr --Cr, Zr --V, and Zr --Sb. Data on twenty compositions for exposures of up to 3000 hr in H₂O at 360 deg C and in steam at 400 and 482 deg C showed three alloys exhibiting less H weight gain than by Zircaloy-2. The various intermetallic phases in the alloys did not play a consistent role in determining the percentage corrosion H taken up by the alloys. Proportion of corrosion H passing through the corrosion films varied from 0.4 to 100%, depending on alloy composition; it variedmore »« less
https://doi.org/10.5006/0010-9312-19.8.285
ZIRCONIUM-NIOBIUM BINARY ALLOYS FOR BOILING WATER REACTOR SERVICE. PART II. CORROSION HYDROGEN EMBRITTLEMENT

Journal Article Klepfer, H H - Journal of Nuclear Materials (Netherlands)

Embrittlement by H produced during corrosion of spongebase, Zr -Ni binary alloys containing up to 4.2 wt% Nb was studied. Thin corrosion films in H/ sub 2/O and in steam were found to allow the passage of about 12% of the corrosionproduced H into the underlying metal; beta-quenched samples continued to show low pickup through thick oxide films, at least up to 454 mg/dm/sup 2/, in steam. Alpha-treated samples in steam showed about 25% pickup through thick films. Total H weight gains were equal to or less than those for Zircaloy-2 in all tests. Hydrogen solubility was apparently higher inmore »« less
https://doi.org/10.1016/0022-3115(63)90170-3

Similar Records