Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding
Abstract
In this work, high purity SiC and SiC/SiC composites coated with commercial TiN, Cr, CrN, or CrN/Cr multilayer coatings were irradiated in Ar or flowing PWR water in the Massachusetts Institute of Technology Nuclear Reactor Laboratory (MITR). Irradiation in Ar was performed in the core. In the water environment, identical samples were placed in one of three different locations: in-core, providing exposure to neutron damage and radiolysis-affected water; above-core, where samples were exposed to radiolysis-affected water but not neutron damage, or outside of the core, where samples were exposed to the coolant water without the effects of radiation. Radiation in Ar revealed significant cracking of all but the TiN coatings, attributed to differential swelling between the coating and substrate. Lattice swelling was not observed in any of the coatings, but 0.2% void swelling was observed in the Cr coating. All of the coatings failed during water exposures in the core. Likewise, CrN/Cr spalled in each condition. Cr was protective, except under radiation damage as a result of cracking, and TiN severely degraded in the core with no coating was found following exposure. A SiC/coating ATF cladding system is anticipated to perform adequately following improvements in coating ductility and purity.
- Authors:
-
- Univ. of Tennessee, Knoxville, TN (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Stony Brook Univ., NY (United States)
- Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign; USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1617463
- Alternate Identifier(s):
- OSTI ID: 1618139; OSTI ID: 1649351
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 536; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; 42 ENGINEERING; SiC; ATF; accident-tolerant fuel cladding; TiN; CrN; Cr; coating; corrosion; neutron irradiation; ceramics; composites
Citation Formats
Doyle, Peter J., Koyanagi, Takaaki, Ang, Caen K., Snead, Lance, Mouche, Peter A., Katoh, Yutai, and Raiman, Stephen S. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. United States: N. p., 2020.
Web. doi:10.1016/j.jnucmat.2020.152203.
Doyle, Peter J., Koyanagi, Takaaki, Ang, Caen K., Snead, Lance, Mouche, Peter A., Katoh, Yutai, & Raiman, Stephen S. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. United States. https://doi.org/10.1016/j.jnucmat.2020.152203
Doyle, Peter J., Koyanagi, Takaaki, Ang, Caen K., Snead, Lance, Mouche, Peter A., Katoh, Yutai, and Raiman, Stephen S. Tue .
"Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding". United States. https://doi.org/10.1016/j.jnucmat.2020.152203. https://www.osti.gov/servlets/purl/1617463.
@article{osti_1617463,
title = {Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding},
author = {Doyle, Peter J. and Koyanagi, Takaaki and Ang, Caen K. and Snead, Lance and Mouche, Peter A. and Katoh, Yutai and Raiman, Stephen S.},
abstractNote = {In this work, high purity SiC and SiC/SiC composites coated with commercial TiN, Cr, CrN, or CrN/Cr multilayer coatings were irradiated in Ar or flowing PWR water in the Massachusetts Institute of Technology Nuclear Reactor Laboratory (MITR). Irradiation in Ar was performed in the core. In the water environment, identical samples were placed in one of three different locations: in-core, providing exposure to neutron damage and radiolysis-affected water; above-core, where samples were exposed to radiolysis-affected water but not neutron damage, or outside of the core, where samples were exposed to the coolant water without the effects of radiation. Radiation in Ar revealed significant cracking of all but the TiN coatings, attributed to differential swelling between the coating and substrate. Lattice swelling was not observed in any of the coatings, but 0.2% void swelling was observed in the Cr coating. All of the coatings failed during water exposures in the core. Likewise, CrN/Cr spalled in each condition. Cr was protective, except under radiation damage as a result of cracking, and TiN severely degraded in the core with no coating was found following exposure. A SiC/coating ATF cladding system is anticipated to perform adequately following improvements in coating ductility and purity.},
doi = {10.1016/j.jnucmat.2020.152203},
journal = {Journal of Nuclear Materials},
number = C,
volume = 536,
place = {United States},
year = {Tue May 05 00:00:00 EDT 2020},
month = {Tue May 05 00:00:00 EDT 2020}
}
Works referenced in this record:
Irradiation creep and swelling of AISI 316 to exposures of 130 dpa at 385–400°C
journal, July 1988
- Garner, F. A.; Porter, D. L.
- Journal of Nuclear Materials, Vol. 155-157
Hydrothermal Corrosion of Coatings on Silicon Carbide in Boiling Water Reactor Conditions
journal, November 2018
- Raiman, Stephen S.; Doyle, Peter; Ang, Caen
- CORROSION, Vol. 75, Issue 2
JENDL-4.0: A New Library for Nuclear Science and Engineering
journal, January 2011
- Shibata, Keiichi; Iwamoto, Osamu; Nakagawa, Tsuneo
- Journal of Nuclear Science and Technology, Vol. 48, Issue 1
Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding
journal, November 2015
- Stone, J. G.; Schleicher, R.; Deck, C. P.
- Journal of Nuclear Materials, Vol. 466
Role of irradiation-induced defects on SiC dissolution in hot water
journal, November 2016
- Kondo, Sosuke; Mouri, Shinichiro; Hyodo, Yoshihiro
- Corrosion Science, Vol. 112
Handbook of SiC properties for fuel performance modeling
journal, September 2007
- Snead, Lance L.; Nozawa, Takashi; Katoh, Yutai
- Journal of Nuclear Materials, Vol. 371, Issue 1-3
Microstructural evolution of neutron irradiated 3C-SiC
journal, August 2017
- Sprouster, D. J.; Koyanagi, T.; Dooryhee, E.
- Scripta Materialia, Vol. 137
Low temperature neutron irradiation effects on microstructure and tensile properties of molybdenum
journal, May 2008
- Li, Meimei; Eldrup, M.; Byun, T. S.
- Journal of Nuclear Materials, Vol. 376, Issue 1
Effect of coating thickness on microstructure, mechanical properties and fracture behaviour of cold sprayed Ti6Al4V coatings on Ti6Al4V substrates
journal, September 2018
- Tan, Adrian Wei-Yee; Sun, Wen; Bhowmik, Ayan
- Surface and Coatings Technology, Vol. 349
Parametric Evaluation of SiC/SiC Composite Cladding with UO2 Fuel for LWR Applications: Fuel Rod Interactions and Impact of Nonuniform Power Profile in Fuel Rod
journal, February 2018
- Singh, G.; Sweet, R.; Brown, N. R.
- Journal of Nuclear Materials, Vol. 499
Residual stress estimation of ceramic thin films by X-ray diffraction and indentation techniques
journal, May 2003
- Atar, Erdem; Sarioglu, Cevat; Demirler, Ugur
- Scripta Materialia, Vol. 48, Issue 9
Chemical Corrosion of Liquid-Phase Sintered SiC in Acidic/Alkaline Solutions Part 1. Corrosion in HNO3 Solution
journal, February 2016
- Zhang, Lei; Zhang, Ming; He, Xinnong
- Journal of Materials Engineering and Performance, Vol. 25, Issue 3
Rietveld refinement guidelines
journal, February 1999
- McCusker, L. B.; Von Dreele, R. B.; Cox, D. E.
- Journal of Applied Crystallography, Vol. 32, Issue 1
Swelling of SiC at intermediate and high irradiation temperatures
journal, August 2007
- Snead, L. L.; Katoh, Y.; Connery, S.
- Journal of Nuclear Materials, Vol. 367-370
Thermal decomposition routes of CrN hard coatings synthesized by reactive arc evaporation and magnetron sputtering
journal, November 2008
- Ernst, W.; Neidhardt, J.; Willmann, H.
- Thin Solid Films, Vol. 517, Issue 2
Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773K up to 5dpa
journal, August 2007
- Ando, M.; Li, M.; Tanigawa, H.
- Journal of Nuclear Materials, Vol. 367-370
Characterization of PVD Cr, CrN, and TiN coatings on SiC
journal, December 2019
- Mouche, P. A.; Ang, C.; Koyanagi, T.
- Journal of Nuclear Materials, Vol. 527
Current status and critical issues for development of SiC composites for fusion applications
journal, August 2007
- Katoh, Y.; Snead, L. L.; Henager, C. H.
- Journal of Nuclear Materials, Vol. 367-370
Thermomechanical characteristics of low activation chromium and chromium alloys
journal, October 1998
- Stamm, H.; Bonansinga, M. R.; Dos Santos Marques, F.
- Journal of Nuclear Materials, Vol. 258-263
Structural stability and thermodynamics of CrN magnetic phases from ab initio calculations and experiment
journal, November 2014
- Zhou, Liangcai; Körmann, Fritz; Holec, David
- Physical Review B, Vol. 90, Issue 18
Radiation-tolerant joining technologies for silicon carbide ceramics and composites
journal, May 2014
- Katoh, Yutai; Snead, Lance L.; Cheng, Ting
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
journal, September 2013
- Pint, B. A.; Terrani, K. A.; Brady, M. P.
- Journal of Nuclear Materials, Vol. 440, Issue 1-3
Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding
journal, April 2018
- Dryepondt, Sebastien; Unocic, Kinga A.; Hoelzer, David T.
- Journal of Nuclear Materials, Vol. 501
Silicon Carbide Oxidation in Steam up to 2 MPa
journal, July 2014
- Terrani, Kurt A.; Pint, Bruce A.; Parish, Chad M.
- Journal of the American Ceramic Society, Vol. 97, Issue 8
Accident tolerant fuel cladding development: Promise, status, and challenges
journal, April 2018
- Terrani, Kurt A.
- Journal of Nuclear Materials, Vol. 501
Mechanical integrity in PVD coatings due to the presence of residual stresses
journal, July 2001
- Teixeira, V.
- Thin Solid Films, Vol. 392, Issue 2
Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating
journal, May 2018
- Ang, Caen; Kemery, Craig; Katoh, Yutai
- Journal of Nuclear Materials, Vol. 503
Irradiation resistance of vacuum arc chromium coatings for zirconium alloy fuel claddings
journal, November 2018
- Kuprin, A. S.; Belous, V. A.; Voyevodin, V. N.
- Journal of Nuclear Materials, Vol. 510
Irradiation-induced effects of proton irradiation on zirconium carbides with different stoichiometries
journal, October 2014
- Huang, Y.; Maier, B. R.; Allen, T. R.
- Nuclear Engineering and Design, Vol. 277
Accident tolerant fuels for LWRs: A perspective
journal, May 2014
- Zinkle, S. J.; Terrani, K. A.; Gehin, J. C.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Irradiation-induced point defects enhance the electrochemical activity of 3C-SiC: An origin of SiC corrosion
journal, June 2018
- Maeda, Yuki; Fukami, Kazuhiro; Kondo, Sosuke
- Electrochemistry Communications, Vol. 91
Influence of microstructure on hydrothermal corrosion of chemically vapor processed SiC composite tubes
journal, August 2017
- Kim, Daejong; Lee, Ho Jung; Jang, Changheui
- Journal of Nuclear Materials, Vol. 492
Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime
journal, February 2018
- Katoh, Yutai; Koyanagi, Takaaki; McDuffee, Joel L.
- Journal of Nuclear Materials, Vol. 499
Swelling and void-induced embrittlement of austenitic stainless steel irradiated to 73–82 dpa at 335–365°C
journal, October 1998
- Porollo, S. I.; Vorobjev, A. N.; Konobeev, Yu. V.
- Journal of Nuclear Materials, Vol. 258-263
Microscopic fracture mechanism of sintered high purity chromium
journal, June 2000
- Matsumoto, Y.; Ohta, S.; Aoki, N.
- Materials Science and Engineering: A, Vol. 285, Issue 1-2
Deformation analysis of SiC-SiC channel box for BWR applications
journal, January 2019
- Singh, G.; Gorton, J.; Schappel, D.
- Journal of Nuclear Materials, Vol. 513
X‐Ray Examination of Brittle Fractures in Extruded Chromium
journal, April 1960
- Weaver, C. W.; Gross, K. A.
- Journal of Applied Physics, Vol. 31, Issue 4
Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure
journal, August 2012
- Cheng, Ting; Keiser, James R.; Brady, Michael P.
- Journal of Nuclear Materials, Vol. 427, Issue 1-3
Long-term corrosion behavior of CVD SiC in 360°C water and 400°C steam
journal, November 2013
- Park, Jeong-Yong; Kim, Il-Hyun; Jung, Yang-Il
- Journal of Nuclear Materials, Vol. 443, Issue 1-3
Structure and properties of TiN coatings
journal, June 1985
- Sundgren, J. -E.
- Thin Solid Films, Vol. 128, Issue 1-2
Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation
journal, October 2015
- Terrani, K. A.; Yang, Y.; Kim, Y. -J.
- Journal of Nuclear Materials, Vol. 465
Thermal expansion of magnetron sputtered TiCxN1-x coatings studied by high-temperature X-ray diffraction
journal, October 2019
- Saringer, Christian; Kickinger, Christoph; Munnik, Frans
- Thin Solid Films, Vol. 688
Microstructure and hydrothermal corrosion behavior of NITE-SiC with various sintering additives in LWR coolant environments
journal, April 2017
- Parish, Chad M.; Terrani, Kurt A.; Kim, Young-Jin
- Journal of the European Ceramic Society, Vol. 37, Issue 4
Effect of irradiation damage on hydrothermal corrosion of SiC
journal, September 2015
- Kondo, Sosuke; Lee, Moonhee; Hinoki, Tatsuya
- Journal of Nuclear Materials, Vol. 464
Irradiation creep of the US Heat 832665 of V–4Cr–4Ti
journal, April 2009
- Li, Meimei; Hoelzer, D. T.; Grossbeck, M. L.
- Journal of Nuclear Materials, Vol. 386-388
Motivation for utilizing new high-performance advanced materials in nuclear energy systems
journal, December 2016
- Zinkle, S. J.; Terrani, K. A.; Snead, L. L.
- Current Opinion in Solid State and Materials Science, Vol. 20, Issue 6
Modeling the impact of radiation-enhanced diffusion on implanted ion profiles
journal, October 2018
- Doyle, Peter J.; Benensky, Kelsa M.; Zinkle, Steven J.
- Journal of Nuclear Materials, Vol. 509
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations
journal, January 2018
- Zinkle, S. J.; Snead, L. L.
- Scripta Materialia, Vol. 143
Uniform corrosion of FeCrAl alloys in LWR coolant environments
journal, October 2016
- Terrani, K. A.; Pint, B. A.; Kim, Y. -J.
- Journal of Nuclear Materials, Vol. 479
Corrosion Behavior of Silicon Carbide in 290oC Water
journal, November 1989
- Hirayama, Hideo; Kawakubo, Takashi; Goto, Akira
- Journal of the American Ceramic Society, Vol. 72, Issue 11
X-ray elastic constants and residual stress of textured titanium nitride coating
journal, November 1992
- Sue, J.
- Surface and Coatings Technology, Vol. 54-55