Material selection for accident tolerant fuel cladding

Pint, B. A.; Terrani, K. A.; Yamamoto, Y.; Snead, L. L.

doi:10.1007/s40553-015-0056-7

Title: Material selection for accident tolerant fuel cladding

Journal Article · 13 September 2015 · Metallurgical and Materials Transactions. E, Materials for Energy Systems

DOI: https://doi.org/10.1007/s40553-015-0056-7 · OSTI ID:1155053

Pint, B. A. ^[1]; Terrani, K. A. ^[1]; Yamamoto, Y. ^[1]; Snead, L. L. ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Alternative cladding materials are being investigated for accident tolerance, which can be defined as >100X improvement (compared to current Zr-based alloys) in oxidation resistance in steam environments at ≥1200°C for short (≤4 h) times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800°C could not be reproduced. Both FeCrAl and MAX phase Ti₂AlC form a protective alumina scale in steam. Therefore, commercial Ti₂AlC that is not single phase, formed a much thicker oxide at 1200°C in steam and significant TiO₂, and therefore may be challenging to use as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475°C, while reducing its Cr content to minimize susceptibility to irradiation assisted Cr-rich α’ formation. The composition effects and critical limits to retaining protective scale formation at >1400°C are still being evaluated.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1155053

Report Number(s):: M3FT-14OR0202361

Journal Information:: Metallurgical and Materials Transactions. E, Materials for Energy Systems, Journal Name: Metallurgical and Materials Transactions. E, Materials for Energy Systems Journal Issue: 3 Vol. 2; ISSN 2196-2936

Publisher:: ASM InternationalCopyright Statement

Country of Publication:: United States

Language:: English

References (33)

The influence of alloying elements on the development and maintenance of protective scales Stott, F. H.; Wood, G. C.; Stringer, J. Oxidation of Metals, Vol. 44, Issue 1-2 https://doi.org/10.1007/BF01046725	journal	August 1995
Microstructure and Residual Stress of Alumina Scale Formed on Ti2AlC at High Temperature in Air Byeon, J. W.; Liu, J.; Hopkins, M. Oxidation of Metals, Vol. 68, Issue 1-2 https://doi.org/10.1007/s11085-007-9063-0	journal	June 2007
Mechanistic-Based Lifetime Predictions for High-Temperature Alloys and Coatings Pint, B. A.; Dryepondt, S.; Put, A. Rouaix-Vande JOM, Vol. 64, Issue 12 https://doi.org/10.1007/s11837-012-0474-2	journal	November 2012
Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications Pint, B. A.; Dryepondt, S.; Unocic, K. A. JOM, Vol. 66, Issue 12 https://doi.org/10.1007/s11837-014-1200-z	journal	November 2014
A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels Mathon, M. H.; de Carlan, Y.; Geoffroy, G. Journal of Nuclear Materials, Vol. 312, Issue 2-3 https://doi.org/10.1016/S0022-3115(02)01630-6	journal	February 2003
The M_N+1AX_N phases: A new class of solids: Thermodynamically stable nanolaminates Barsoum, Michel W. Progress in Solid State Chemistry, Vol. 28, Issue 1-4, p. 201-281 https://doi.org/10.1016/S0079-6786(00)00006-6	journal	January 2000
Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure Cheng, Ting; Keiser, James R.; Brady, Michael P. Journal of Nuclear Materials, Vol. 427, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.05.007	journal	August 2012
Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure Terrani, Kurt A.; Parish, Chad M.; Shin, Dongwon Journal of Nuclear Materials, Vol. 438, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.03.006	journal	July 2013
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments Pint, B. A.; Terrani, K. A.; Brady, M. P. Journal of Nuclear Materials, Vol. 440, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.05.047	journal	September 2013
Post-quench ductility evaluation of Zircaloy-4 and select iron alloys under design basis and extended LOCA conditions Yan, Y.; Keiser, J. R.; Terrani, K. A. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.05.071	journal	May 2014
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding Terrani, K. A.; Zinkle, S. J.; Snead, L. L. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.06.041	journal	May 2014
High temperature oxidation of molybdenum in water vapor environments Nelson, A. T.; Sooby, E. S.; Kim, Y. -J. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.043	journal	May 2014
Accident tolerant fuels for LWRs: A perspective Zinkle, S. J.; Terrani, K. A.; Gehin, J. C. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.005	journal	May 2014
Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction Farmer, M. T.; Leibowitz, L.; Terrani, K. A. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.022	journal	May 2014
Thermo-mechanical analysis of LWR SiC/SiC composite cladding Ben-Belgacem, M.; Richet, V.; Terrani, K. A. Journal of Nuclear Materials, Vol. 447, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.01.006	journal	April 2014
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.023	journal	October 2015
On the α–α′ miscibility gap of Fe–Cr alloys Bonny, G.; Terentyev, D.; Malerba, L. Scripta Materialia, Vol. 59, Issue 11 https://doi.org/10.1016/j.scriptamat.2008.08.008	journal	December 2008
The M_n+1AX_n phases: Materials science and thin-film processing Eklund, Per; Beckers, Manfred; Jansson, Ulf Thin Solid Films, Vol. 518, Issue 8, p. 1851-1878 https://doi.org/10.1016/j.tsf.2009.07.184	journal	February 2010
Reaction of Flowing Steam with Refractory Metals. ^1,2 I. Molybdenum (1100-1700°) Kilpatrick, Martin; Lott, Stanley K. The Journal of Physical Chemistry, Vol. 69, Issue 5 https://doi.org/10.1021/j100889a032	journal	May 1965
The Volatilization of Molybdenum in the Presence of Water Vapor Belton, G. R.; Jordan, A. S. The Journal of Physical Chemistry, Vol. 69, Issue 6 https://doi.org/10.1021/j100890a043	journal	June 1965
Silicon Carbide Oxidation in Steam up to 2 MPa Terrani, Kurt A.; Pint, Bruce A.; Parish, Chad M. Journal of the American Ceramic Society, Vol. 97, Issue 8 https://doi.org/10.1111/jace.13094	journal	July 2014
Oxidation of Molybdenum 550° to 1700°C Gulbransen, E. A.; Andrew, K. F.; Brassart, F. A. Journal of The Electrochemical Society, Vol. 110, Issue 9 https://doi.org/10.1149/1.2425918	journal	January 1963
Oxidation Studies on the Iron-Chromium-Aluminum Heater Alloys Gulbransen, Earl A.; Andrew, Kenneth F. Journal of The Electrochemical Society, Vol. 106, Issue 4 https://doi.org/10.1149/1.2427333	journal	January 1959
Long-Term Oxidation of Ti ₂ AlC in Air and Water Vapor at 1000–1300°C Temperature Range Basu, S.; Obando, N.; Gowdy, A. Journal of The Electrochemical Society, Vol. 159, Issue 2 https://doi.org/10.1149/2.052202jes	journal	January 2011
Effect of steam on high temperature oxidation behaviour of alumina-forming alloys Pint, B. A.; Unocic, K. A.; Terrani, K. A. Materials at High Temperatures, Vol. 32, Issue 1-2 https://doi.org/10.1179/0960340914Z.00000000058	journal	January 2015
Microstructure and environmental resistance of low Cr ODS FeCrAl Unocic, K. A.; Hoelzer, D. T.; Pint, B. A. Materials at High Temperatures, Vol. 32, Issue 1-2 https://doi.org/10.1179/0960340914Z.00000000088	journal	January 2015
25 years of Materials Science and Technology Knott, John Materials Science and Technology, Vol. 25, Issue 1 https://doi.org/10.1179/174328409X397247	journal	January 2009
Insight from Fukushima Daiichi Unit 3 Investigations Using MELCOR Robb, Kevin R.; Francis, Matthew W.; Ott, Larry J. Nuclear Technology, Vol. 186, Issue 2 https://doi.org/10.13182/NT13-43	journal	May 2014
Insight from Fukushima Daiichi Unit 3 Investigations Using MELCOR Robb, Kevin R.; Francis, Matthew W.; Ott, Larry J. Nuclear Technology, Vol. 186, Issue 2 https://doi.org/10.13182/nt13-43	journal	May 2014
Recommended Property and Reaction Kinetics Data for Use in Evaluating a Light-Water-Cooled Reactor Loss-of-Coolant Incident Involving Zircaloy-4-or 304-SS-CLAUD UO₂ Brassfield, H. C.; White, J. F.; Sjodahl, L. https://doi.org/10.2172/4521035	report	April 1968
Zirconium metal-water oxidation kinetics. IV. Reaction rate studies. [BWR:PWR] Cathcart, J. V.; Pawel, R. E.; McKee, R. A. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States) https://doi.org/10.2172/7317596	report	July 1977
Morphologies of oxide growth and exfoliation in superheater and reheater tubing of steam boiler Wright, Ian G.; Barry Dooley, R. Materials at High Temperatures, Vol. 28, Issue 1 https://doi.org/10.3184/096034011X12982937656387	journal	March 2011
High temperature oxidation behaviour of Ti ₂ AlC ceramic at 1200°C Song, G. M.; Schnabel, V.; Kwakernaak, C. Materials at High Temperatures, Vol. 29, Issue 3 https://doi.org/10.3184/096034012X13348496462140	journal	September 2012

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A study of irradiation effects in TiO ₂ using molecular dynamics simulation and complementary in situ transmission electron microscopy Cowen, Benjamin J.; El-Genk, Mohamed S.; Hattar, Khalid Journal of Applied Physics, Vol. 124, Issue 9 https://doi.org/10.1063/1.5045491	journal	September 2018

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