Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding
Abstract
Iron-chromium-aluminum (FeCrAl) alloys such as APMT (advanced powder metallurgy tubing) are candidate materials to replace zirconium alloys for the light water reactor fuel cladding. This alloy meets the requirements to be a material more tolerant of high-temperature accidents than the current zirconium alloys. One concern is that the use of FeCrAl may result in an increase in tritium presence in the coolant compared to the current design. The aim of the current research was to obtain effective diffusion coefficients (Deff) for hydrogen through APMT using the Devanathan-Stachurski cell. Results showed that at 30°C the Deff value was 2.8 × 10-8 cm2/s. Results also showed a linear relationship between the permeated hydrogen flux and the inverse of the test specimen thickness, which demonstrated the validity of the permeation measurements.
- Authors:
-
- DNV GL, Dublin, OH (United States)
- General Electric Co., Schenectady, NY (United States)
- Publication Date:
- Research Org.:
- General Electric Co., Boston, MA (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1981286
- Grant/Contract Number:
- NE0009047
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Corrosion
- Additional Journal Information:
- Journal Volume: 78; Journal Issue: 5; Journal ID: ISSN 0010-9312
- Publisher:
- NACE International
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; Materials Science; Metallurgy & Metallurgical Engineering; Advanced powder metallurgy tubing; Devanathan-Stachurski cell; Effective diffusivity; Iron-chromium-aluminum; Hydrogen permeation
Citation Formats
Evans, K. J., and Rebak, R. B. Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding. United States: N. p., 2022.
Web. doi:10.5006/4018.
Evans, K. J., & Rebak, R. B. Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding. United States. https://doi.org/10.5006/4018
Evans, K. J., and Rebak, R. B. Thu .
"Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding". United States. https://doi.org/10.5006/4018. https://www.osti.gov/servlets/purl/1981286.
@article{osti_1981286,
title = {Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding},
author = {Evans, K. J. and Rebak, R. B.},
abstractNote = {Iron-chromium-aluminum (FeCrAl) alloys such as APMT (advanced powder metallurgy tubing) are candidate materials to replace zirconium alloys for the light water reactor fuel cladding. This alloy meets the requirements to be a material more tolerant of high-temperature accidents than the current zirconium alloys. One concern is that the use of FeCrAl may result in an increase in tritium presence in the coolant compared to the current design. The aim of the current research was to obtain effective diffusion coefficients (Deff) for hydrogen through APMT using the Devanathan-Stachurski cell. Results showed that at 30°C the Deff value was 2.8 × 10-8 cm2/s. Results also showed a linear relationship between the permeated hydrogen flux and the inverse of the test specimen thickness, which demonstrated the validity of the permeation measurements.},
doi = {10.5006/4018},
journal = {Corrosion},
number = 5,
volume = 78,
place = {United States},
year = {Thu Mar 24 00:00:00 EDT 2022},
month = {Thu Mar 24 00:00:00 EDT 2022}
}
Works referenced in this record:
Diffusion of a gas through a membrane
journal, August 1992
- Fan, D.; White, R. E.; Gruberger, N.
- Journal of Applied Electrochemistry, Vol. 22, Issue 8
The solubility and diffusivity of hydrogen in well-annealed and deformed iron
journal, July 1983
- Kiuchi, K.; McLellan, R. B.
- Acta Metallurgica, Vol. 31, Issue 7
Hydrogen transport in a duplex stainless steel
journal, July 2000
- Owczarek, E.; Zakroczymski, T.
- Acta Materialia, Vol. 48, Issue 12
Hydrogen permeation characteristics of some Fe-Cr-Al alloys
journal, January 1983
- Van Deventer, E. H.; Maroni, V. A.
- Journal of Nuclear Materials, Vol. 113, Issue 1
Performance degradation of candidate accident-tolerant cladding under corrosive environment
journal, August 2017
- Nagase, Fumihisa; Sakamoto, Kan; Yamashita, Shinichiro
- Corrosion Reviews, Vol. 35, Issue 3
Al–Cr–O thin films as an efficient hydrogen barrier
journal, July 2008
- Levchuk, Denis; Bolt, Harald; Döbeli, Max
- Surface and Coatings Technology, Vol. 202, Issue 20
Hydrogen Diffusion in FeCrAl Alloys for Light Water Reactors Cladding Applications
conference, July 2016
- Rebak, Raul B.; Kim, Young-Jin
- Volume 6B: Materials and Fabrication
Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants
journal, January 2017
- Rebak, Raul B.
- EPJ Nuclear Sciences & Technologies, Vol. 3
The effect of temperature and H 2 S concentration on hydrogen diffusion and trapping in a 13% chromium martensitic stainless steel in acidified NaCl
journal, January 1990
- Turnbull, A.; Carroll, M. W.
- Corrosion Science, Vol. 30, Issue 6-7
On the mechanism of hydrogen permeation in iron in alkaline medium
journal, January 1998
- Brass, A. M.; Collet-Lacoste, J. R.
- Acta Materialia, Vol. 46, Issue 3
Microstructure and tensile behavior of powder metallurgy FeCrAl accident tolerant fuel cladding
journal, March 2022
- Huang, Shenyan; Dolley, Evan; An, Ke
- Journal of Nuclear Materials, Vol. 560
On the effective diffusivity of hydrogen in low alloy steels
journal, November 1995
- Griffiths, A. J.; Turnbull, A.
- Corrosion Science, Vol. 37, Issue 11
Necessity of a palladium coating to ensure hydrogen oxidation during electrochemical permeation measurements on iron
journal, May 1995
- Manolatos, P.; Jerome, M.; Galland, J.
- Electrochimica Acta, Vol. 40, Issue 7
Permeability of iron to hydrogen cathodically generated in 0.1 M NaoH
journal, April 1985
- Zakroczymski, T.
- Scripta Metallurgica, Vol. 19, Issue 4
The Permeation of Hydrogen Isotopes through Structural Metals at Low Pressures and through Metals with Oxide Film Barriers
journal, April 1974
- Strehlow, R. A.; Savage, H. C.
- Nuclear Technology, Vol. 22, Issue 1