Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing
Abstract
Here assessment of burst characteristics of accident-tolerant fuel (ATF) claddings is essential to evaluate the safety margins of nuclear reactors, and better understanding can enable accelerated licensing for reactor concepts that include the new materials. Therefore, this study investigated the burst behavior of an ATF candidate of C26M, which is an iron–chromium–aluminum alloy (FeCrAl) under transient testing like the simulated loss-of-coolant accident (LOCA) conditions, except the water-quenching phase, in light-water reactors (LWRs). The effect of LOCA specimen length was assessed in terms of post-burst tube parameters. No critical length effect was determined on the burst pressure, burst location, and burst size measurements. Burst temperature showed larger variation likely due to its measurement approach used in this study. The post-test diametral strain was identified as the critical parameter to reduce the specimen length as compared to tube burst length or width. Postmortem optical metrology and digital image correlation were employed to determine the local strain-state during the simulated LOCA, which showed the loading path was close to equibiaxial conditions in regions away from the burst location, rather than internally pressurized conditions (or “plane-strain” tension). Pst-test microstructural characterizations of the FeCrAl revealed that ductile damage was present at the edge of themore »
- Authors:
-
[1];
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1846541
- Alternate Identifier(s):
- OSTI ID: 1837452
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 560; Journal Issue: 1; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; iron-chromium-aluminum; FeCrAl alloys; failure behavior; burst characteristics; transient testing; simulated-LOCA
Citation Formats
Garrison, Ben E., Cinbiz, Mahmut Nedim, Gussev, Maxim N., and Linton, Kory D. Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing. United States: N. p., 2021.
Web. doi:10.1016/j.jnucmat.2021.153488.
Garrison, Ben E., Cinbiz, Mahmut Nedim, Gussev, Maxim N., & Linton, Kory D. Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing. United States. https://doi.org/10.1016/j.jnucmat.2021.153488
Garrison, Ben E., Cinbiz, Mahmut Nedim, Gussev, Maxim N., and Linton, Kory D. Sat .
"Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing". United States. https://doi.org/10.1016/j.jnucmat.2021.153488. https://www.osti.gov/servlets/purl/1846541.
@article{osti_1846541,
title = {Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing},
author = {Garrison, Ben E. and Cinbiz, Mahmut Nedim and Gussev, Maxim N. and Linton, Kory D.},
abstractNote = {Here assessment of burst characteristics of accident-tolerant fuel (ATF) claddings is essential to evaluate the safety margins of nuclear reactors, and better understanding can enable accelerated licensing for reactor concepts that include the new materials. Therefore, this study investigated the burst behavior of an ATF candidate of C26M, which is an iron–chromium–aluminum alloy (FeCrAl) under transient testing like the simulated loss-of-coolant accident (LOCA) conditions, except the water-quenching phase, in light-water reactors (LWRs). The effect of LOCA specimen length was assessed in terms of post-burst tube parameters. No critical length effect was determined on the burst pressure, burst location, and burst size measurements. Burst temperature showed larger variation likely due to its measurement approach used in this study. The post-test diametral strain was identified as the critical parameter to reduce the specimen length as compared to tube burst length or width. Postmortem optical metrology and digital image correlation were employed to determine the local strain-state during the simulated LOCA, which showed the loading path was close to equibiaxial conditions in regions away from the burst location, rather than internally pressurized conditions (or “plane-strain” tension). Pst-test microstructural characterizations of the FeCrAl revealed that ductile damage was present at the edge of the outer radial surface while the rest of the material was ruptured via cleavage at LOCA burst temperatures. Furthermore, internal grain boundary cracks were observed at locations away from the tube burst region. This behavior was considered to occur during the cooling down period of the simulated LOCA test. Overall, this study aimed to provide essential data for fuel performance code development by considering micromechanics of the deformation and failure.},
doi = {10.1016/j.jnucmat.2021.153488},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 560,
place = {United States},
year = {Sat Dec 18 00:00:00 EST 2021},
month = {Sat Dec 18 00:00:00 EST 2021}
}
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Works referenced in this record:
Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions
journal, December 2004
- Nagase, Fumihisa; Fuketa, Toyoshi
- Journal of Nuclear Science and Technology, Vol. 41, Issue 12
Cladding burst behavior of Fe-based alloys under LOCA
journal, March 2016
- Massey, Caleb P.; Terrani, Kurt A.; Dryepondt, Sebastien N.
- Journal of Nuclear Materials, Vol. 470
The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors
journal, January 2017
- Brown, Nicholas R.; Wysocki, Aaron J.; Terrani, Kurt A.
- Annals of Nuclear Energy, Vol. 99
Precipitation of α′ in neutron irradiated commercial FeCrAl alloys
journal, January 2018
- Field, Kevin G.; Littrell, Kenneth C.; Briggs, Samuel A.
- Scripta Materialia, Vol. 142
Oxidation Studies on the Iron-Chromium-Aluminum Heater Alloys
journal, January 1959
- Gulbransen, Earl A.; Andrew, Kenneth F.
- Journal of The Electrochemical Society, Vol. 106, Issue 4
An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading
journal, May 2019
- Cinbiz, M. Nedim; Gussev, Maxim; Linton, Kory
- Annals of Nuclear Energy, Vol. 127
Impact of neutron irradiation on mechanical performance of FeCrAl alloy laser-beam weldments
journal, June 2018
- Gussev, M. N.; Cakmak, E.; Field, K. G.
- Journal of Nuclear Materials, Vol. 504
The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)
journal, May 2011
- Desquines, J.; Koss, D. A.; Motta, A. T.
- Journal of Nuclear Materials, Vol. 412, Issue 2
A model to predict the failure of zircaloy-4 fuel sheathing during postulated loca conditions
journal, February 1984
- Rosinger, H. E.
- Journal of Nuclear Materials, Vol. 120, Issue 1
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
journal, May 2017
- Briggs, Samuel A.; Edmondson, Philip D.; Littrell, Kenneth C.
- Acta Materialia, Vol. 129
Accident tolerant fuel cladding development: Promise, status, and challenges
journal, April 2018
- Terrani, Kurt A.
- Journal of Nuclear Materials, Vol. 501
Characterization of stress-rupture behavior of nuclear-grade C26M2 FeCrAl alloy for accident-tolerant fuel cladding via burst testing
journal, July 2020
- Joshi, P.; Kombaiah, B.; Cinbiz, M. N.
- Materials Science and Engineering: A, Vol. 791
The PROMETRA Program: Fuel Cladding Mechanical Behavior under High Strain Rate
journal, March 2007
- Cazalis, B.; Desquines, J.; Poussard, C.
- Nuclear Technology, Vol. 157, Issue 3
Integral LOCA fragmentation test on high-burnup fuel
journal, October 2020
- Capps, Nathan; Yan, Yong; Raftery, Alicia
- Nuclear Engineering and Design, Vol. 367
Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys
journal, February 2018
- Sun, Zhiqian; Edmondson, Philip D.; Yamamoto, Yukinori
- Acta Materialia, Vol. 144
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
journal, December 2015
- Yamamoto, Y.; Pint, B. A.; Terrani, K. A.
- Journal of Nuclear Materials, Vol. 467
Four-point-bend tests on high-burnup advanced fuel cladding tubes after exposure to simulated LOCA conditions
journal, February 2020
- Narukawa, Takafumi; Amaya, Masaki
- Journal of Nuclear Science and Technology, Vol. 57, Issue 7
Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions
journal, December 2021
- Bell, S. B.; Kane, K. A.; Massey, C. P.
- Journal of Nuclear Materials, Vol. 557
Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions
journal, October 2020
- Brown, Nicholas R.; Garrison, Benton E.; Lowden, Richard R.
- Journal of Nuclear Materials, Vol. 539