Accident tolerant fuel cladding development: Promise, status, and challenges

Terrani, Kurt A.

doi:10.1016/j.jnucmat.2017.12.043

Title: Accident tolerant fuel cladding development: Promise, status, and challenges

Journal Article · Sat Jan 13 00:00:00 EST 2018 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.12.043· OSTI ID:1471930

Terrani, Kurt A. ^[1]

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

The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby enhancing safety margins during severe accidents, is laid out. A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding, and silicon carbide fiber–reinforced silicon carbide matrix composite cladding, is offered. Technical challenges and data gaps for each of these cladding technologies are highlighted. Full development towards commercial deployment of these technologies is identified as a high priority for the nuclear industry.

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

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1471930

Alternate ID(s):: OSTI ID: 1506714

Journal Information:: Journal of Nuclear Materials, Vol. 501, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 364 works

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References (174)

Thermal Neutron Capture Cross Sections Pomerance, H. Physical Review, Vol. 83, Issue 3 https://doi.org/10.1103/PhysRev.83.641	journal	August 1951
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
The Future of Low-Carbon Electricity Greenblatt, Jeffery B.; Brown, Nicholas R.; Slaybaugh, Rachel Annual Review of Environment and Resources, Vol. 42, Issue 1 https://doi.org/10.1146/annurev-environ-102016-061138	journal	October 2017
Fuel R & D to Improve Fuel Reliability Yang, Rosa; Cheng, Bo; Deshon, Jeff Journal of Nuclear Science and Technology, Vol. 43, Issue 9 https://doi.org/10.1080/18811248.2006.9711181	journal	September 2006
Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding Motta, Arthur T.; Couet, Adrien; Comstock, Robert J. Annual Review of Materials Research, Vol. 45, Issue 1 https://doi.org/10.1146/annurev-matsci-070214-020951	journal	July 2015
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
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions Ott, L. J.; Robb, K. R.; Wang, D. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.052	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
Modification of MELCOR for severe accident analysis of candidate accident tolerant cladding materials Merrill, Brad J.; Bragg-Sitton, Shannon M.; Humrickhouse, Paul W. Nuclear Engineering and Design, Vol. 315 https://doi.org/10.1016/j.nucengdes.2017.02.021	journal	April 2017
Research and Development Methodology for Practical Use of Accident Tolerant Fuel in Light Water Reactors Kurata, Masaki Nuclear Engineering and Technology, Vol. 48, Issue 1 https://doi.org/10.1016/j.net.2015.12.004	journal	February 2016
KAERI’s Development of LWR Accident-Tolerant Fuel Koo, Yang-Hyun; Yang, Jae-Ho; Park, Jeong-Yong Nuclear Technology, Vol. 186, Issue 2 https://doi.org/10.13182/NT13-89	journal	May 2014
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
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
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 Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600–1200 °C Steinbrück, Martin; Vér, Nóra; Große, Mirco Oxidation of Metals, Vol. 76, Issue 3-4 https://doi.org/10.1007/s11085-011-9249-3	journal	March 2011
The Effect of Oxide Volatilization on the Oxidation Kinetics of Cr and Fe-Cr Alloys Tedmon, C. S. Journal of The Electrochemical Society, Vol. 113, Issue 8 https://doi.org/10.1149/1.2424115	journal	January 1966
Alumina Volatility in Water Vapor at Elevated Temperatures Opila, Elizabeth J.; Myers, Dwight L. Journal of the American Ceramic Society, Vol. 87, Issue 9 https://doi.org/10.1111/j.1551-2916.2004.01701.x	journal	September 2004
The effect of H2O gas on volatilities of planet-forming major elements: I. Experimental determination of thermodynamic properties of Ca-, Al-, and Si-hydroxide gas molecules and its application to the solar nebula Hashimoto, Akihiko Geochimica et Cosmochimica Acta, Vol. 56, Issue 1 https://doi.org/10.1016/0016-7037(92)90148-C	journal	January 1992
Mechanisms of irradiation growth of alpha-zirconium alloys Holt, R. A. Journal of Nuclear Materials, Vol. 159 https://doi.org/10.1016/0022-3115(88)90099-2	journal	October 1988
Irradiation-induced densification of UO2 pellet fuel Freshley, M. D.; Brite, D. W.; Daniel, J. L. Journal of Nuclear Materials, Vol. 62, Issue 2-3 https://doi.org/10.1016/0022-3115(76)90013-1	journal	November 1976
Experimental Observations on Fuel Pellet Performance at High Burnup Serna, Juan J.; Tolonen, Pekka; Abeta, Sadaaki Journal of Nuclear Science and Technology, Vol. 43, Issue 9 https://doi.org/10.1080/18811248.2006.9711194	journal	September 2006
Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review Cox, B. Journal of Nuclear Materials, Vol. 172, Issue 3 https://doi.org/10.1016/0022-3115(90)90282-R	journal	August 1990
Cracking of cladding tubes caused by power ramping and by laboratory stress corrosion experiments Videm, K.; Lunde, L.; Hollowell, T. Journal of Nuclear Materials, Vol. 87, Issue 2-3 https://doi.org/10.1016/0022-3115(79)90562-2	journal	December 1979
The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors Brown, Nicholas R.; Wysocki, Aaron J.; Terrani, Kurt A. Annals of Nuclear Energy, Vol. 99 https://doi.org/10.1016/j.anucene.2016.09.033	journal	January 2017
Radiation-Induced Creep of UO2 Solomon, A. A. Journal of the American Ceramic Society, Vol. 56, Issue 3 https://doi.org/10.1111/j.1151-2916.1973.tb15435.x	journal	March 1973
Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 358°C Cockeram, B. V.; Smith, R. W.; Leonard, K. J. Journal of Nuclear Materials, Vol. 418, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.07.006	journal	November 2011
Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 377–440°C Cockeram, B. V.; Leonard, K. J.; Byun, T. S. Journal of Nuclear Materials, Vol. 449, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.03.004	journal	June 2014
Tensile properties of candidate SNS target container materials after proton and neutron irradiation in the LANSCE accelerator Farrell, K.; Byun, T. S. Journal of Nuclear Materials, Vol. 296, Issue 1-3 https://doi.org/10.1016/S0022-3115(01)00515-3	journal	July 2001
Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test Nagase, Fumihisa; Fuketa, Toyoshi Journal of Nuclear Science and Technology, Vol. 42, Issue 1 https://doi.org/10.1080/18811248.2005.9726364	journal	January 2005
Materials challenges in nuclear energy Zinkle, S. J.; Was, G. S. Acta Materialia, Vol. 61, Issue 3 https://doi.org/10.1016/j.actamat.2012.11.004	journal	February 2013
Fuels for sodium-cooled fast reactors: US perspective Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.010	journal	September 2007
Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics Couet, Adrien; Motta, Arthur T.; Comstock, Robert J. Journal of Nuclear Materials, Vol. 451, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.03.001	journal	August 2014
The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents Terrani, Kurt A.; Wang, Dean; Ott, Larry J. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.051	journal	May 2014
Failure of high burnup fuels under reactivity-initiated accident conditions Sugiyama, Tomoyuki; Umeda, Miki; Fuketa, Toyoshi Annals of Nuclear Energy, Vol. 36, Issue 3 https://doi.org/10.1016/j.anucene.2008.12.003	journal	April 2009
Comparative Analysis of Station Blackout Accident Progression in Typical pwr, bwr, and phwr Park, Soo-Yong; Ahn, Kwang-Il Nuclear Engineering and Technology, Vol. 44, Issue 3 https://doi.org/10.5516/NET.03.2011.046	journal	April 2012
Current knowledge on core degradation phenomena, a review Hofmann, P. Journal of Nuclear Materials, Vol. 270, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00899-X	journal	April 1999
Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings Tang, Chongchong; Stueber, Michael; Seifert, Hans Juergen Corrosion Reviews, Vol. 35, Issue 3 https://doi.org/10.1515/corrrev-2017-0010	journal	August 2017
Mechanical analysis of surface-coated zircaloy cladding Lee, Youho; Lee, Jeong Ik; No, Hee Cheon Nuclear Engineering and Technology, Vol. 49, Issue 5 https://doi.org/10.1016/j.net.2017.03.012	journal	August 2017
Neutronic evaluation of coating and cladding materials for accident tolerant fuels Younker, Ian; Fratoni, Massimiliano Progress in Nuclear Energy, Vol. 88 https://doi.org/10.1016/j.pnucene.2015.11.006	journal	April 2016
Critical heat flux for SiC- and Cr-coated plates under atmospheric condition Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Taeseung Annals of Nuclear Energy, Vol. 76 https://doi.org/10.1016/j.anucene.2014.09.046	journal	February 2015
Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.030	journal	October 2015
Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-4 Daub, K.; Van Nieuwenhove, R.; Nordin, H. Journal of Nuclear Materials, Vol. 467 https://doi.org/10.1016/j.jnucmat.2015.09.041	journal	December 2015
Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air Kuprin, А. S.; Belous, V. А.; Voyevodin, V. N. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.016	journal	October 2015
High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings Park, Jung-Hwan; Kim, Hyun-Gil; Park, Jeong-yong Surface and Coatings Technology, Vol. 280 https://doi.org/10.1016/j.surfcoat.2015.09.022	journal	October 2015
Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions Park, Dong Jun; Kim, Hyun Gil; Jung, Yang Il Journal of Nuclear Materials, Vol. 482 https://doi.org/10.1016/j.jnucmat.2016.10.021	journal	December 2016
Designing Radiation Resistance in Materials for Fusion Energy Zinkle, S. J.; Snead, L. L. Annual Review of Materials Research, Vol. 44, Issue 1 https://doi.org/10.1146/annurev-matsci-070813-113627	journal	July 2014
Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures Steinbrück, Martin Journal of Nuclear Materials, Vol. 392, Issue 3 https://doi.org/10.1016/j.jnucmat.2009.04.018	journal	August 2009
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
Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding Maier, Benjamin R.; Garcia-Diaz, Brenda L.; Hauch, Benjamin Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.06.028	journal	November 2015
Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate Yeom, Hwasung; Hauch, Benjamin; Cao, Guoping Thin Solid Films, Vol. 615 https://doi.org/10.1016/j.tsf.2016.07.024	journal	September 2016
Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding Alat, Ece; Motta, Arthur T.; Comstock, Robert J. Surface and Coatings Technology, Vol. 281 https://doi.org/10.1016/j.surfcoat.2015.08.062	journal	November 2015
Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding Alat, Ece; Motta, Arthur T.; Comstock, Robert J. Journal of Nuclear Materials, Vol. 478 https://doi.org/10.1016/j.jnucmat.2016.05.021	journal	September 2016
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
Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials Ang, Caen; Silva, Chinthaka; Shih, Chunghao Scripta Materialia, Vol. 114 https://doi.org/10.1016/j.scriptamat.2015.11.008	journal	March 2016
Phase stability, swelling, microstructure and strength of Ti3SiC2-TiC ceramics after low dose neutron irradiation Ang, Caen; Zinkle, Steven; Shih, Chunghao Journal of Nuclear Materials, Vol. 483 https://doi.org/10.1016/j.jnucmat.2016.10.036	journal	January 2017
Undoped and ytterbium-doped titanium aluminum nitride coatings for improved oxidation behavior of nuclear fuel cladding Brova, Michael J.; Alat, Ece; Pauley, Mark A. Surface and Coatings Technology, Vol. 331 https://doi.org/10.1016/j.surfcoat.2017.09.076	journal	December 2017
Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors Walters, Leon C.; Seidel, B. R.; Kittel, J. Howard Nuclear Technology, Vol. 65, Issue 2 https://doi.org/10.13182/NT84-A33408	journal	May 1984
Steam Oxidation Evaluation of Fe–Cr Alloys for Accident Tolerant Nuclear Fuel Cladding Pint, B. A.; Unocic, K. A. Oxidation of Metals, Vol. 87, Issue 3-4 https://doi.org/10.1007/s11085-017-9754-0	journal	March 2017
The 885° f (475° c) embrittlement of ferritic stainless steels Grobner, P. J. Metallurgical Transactions, Vol. 4, Issue 1 https://doi.org/10.1007/BF02649625	journal	January 1973
α′ precipitation in neutron-irradiated Fe–Cr alloys Bachhav, Mukesh; Robert Odette, G.; Marquis, Emmanuelle A. Scripta Materialia, Vol. 74 https://doi.org/10.1016/j.scriptamat.2013.10.001	journal	March 2014
Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors George, Nathan Michael; Terrani, Kurt; Powers, Jeff Annals of Nuclear Energy, Vol. 75 https://doi.org/10.1016/j.anucene.2014.09.005	journal	January 2015
The development of alumina-forming austenitic stainless steels for high-temperature structural use Brady, M. P.; Yamamoto, Y.; Santella, M. L. JOM, Vol. 60, Issue 7 https://doi.org/10.1007/s11837-008-0083-2	journal	July 2008
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
Performance of FeCrAl for accident-tolerant fuel cladding in high-temperature steam Pint, Bruce A. Corrosion Reviews, Vol. 35, Issue 3 https://doi.org/10.1515/corrrev-2016-0067	journal	August 2017
Effect of Al and Cr Content on Air and Steam Oxidation of FeCrAl Alloys and Commercial APMT Alloy Unocic, Kinga A.; Yamamoto, Yukinori; Pint, Bruce A. Oxidation of Metals, Vol. 87, Issue 3-4 https://doi.org/10.1007/s11085-017-9745-1	journal	March 2017
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors Yamamoto, Y.; Pint, B. A.; Terrani, K. A. Journal of Nuclear Materials, Vol. 467 https://doi.org/10.1016/j.jnucmat.2015.10.019	journal	December 2015
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
Irradiation-enhanced α′ precipitation in model FeCrAl alloys Edmondson, P. D.; Briggs, S. A. Scripta Materialia, Vol. 116 https://doi.org/10.1016/j.scriptamat.2016.02.002	journal	April 2016
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys Briggs, Samuel A.; Edmondson, Philip D.; Littrell, Kenneth C. Acta Materialia, Vol. 129 https://doi.org/10.1016/j.actamat.2017.02.077	journal	May 2017
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys Field, Kevin G.; Briggs, Samuel A.; Sridharan, Kumar Journal of Nuclear Materials, Vol. 489 https://doi.org/10.1016/j.jnucmat.2017.03.038	journal	June 2017
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
Performance degradation of candidate accident-tolerant cladding under corrosive environment Nagase, Fumihisa; Sakamoto, Kan; Yamashita, Shinichiro Corrosion Reviews, Vol. 35, Issue 3 https://doi.org/10.1515/corrrev-2017-0014	journal	August 2017
Design, properties, and weldability of advanced oxidation-resistant FeCrAl alloys Gussev, M. N.; Field, K. G.; Yamamoto, Y. Materials & Design, Vol. 129 https://doi.org/10.1016/j.matdes.2017.05.009	journal	September 2017
Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels McMurray, J. W.; Hu, R.; Ushakov, S. V. Journal of Nuclear Materials, Vol. 492 https://doi.org/10.1016/j.jnucmat.2017.05.016	journal	August 2017
Microstructural control of FeCrAl alloys using Mo and Nb additions Sun, Zhiqian; Bei, Hongbin; Yamamoto, Yukinori Materials Characterization, Vol. 132 https://doi.org/10.1016/j.matchar.2017.08.008	journal	October 2017
Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication Sun, Zhiqian; Yamamoto, Yukinori Materials Science and Engineering: A, Vol. 700 https://doi.org/10.1016/j.msea.2017.06.036	journal	July 2017
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
Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions Yano, Y.; Tanno, T.; Oka, H. Journal of Nuclear Materials, Vol. 487 https://doi.org/10.1016/j.jnucmat.2017.02.021	journal	April 2017
Deformation behavior of laser welds in high temperature oxidation resistant Fe–Cr–Al alloys for fuel cladding applications Field, Kevin G.; Gussev, Maxim N.; Yamamoto, Yukinori Journal of Nuclear Materials, Vol. 454, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.08.013	journal	November 2014
Uniform corrosion of FeCrAl alloys in LWR coolant environments Terrani, K. A.; Pint, B. A.; Kim, Y. -J. Journal of Nuclear Materials, Vol. 479 https://doi.org/10.1016/j.jnucmat.2016.06.047	journal	October 2016
Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments Rebak, Raul B.; Larsen, Michael; Kim, Young-Jin Corrosion Reviews, Vol. 35, Issue 3 https://doi.org/10.1515/corrrev-2017-0011	journal	August 2017
A proposed method of calculating displacement dose rates Norgett, M. J.; Robinson, M. T.; Torrens, I. M. Nuclear Engineering and Design, Vol. 33, Issue 1 https://doi.org/10.1016/0029-5493(75)90035-7	journal	August 1975
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions Gamble, K. A.; Barani, T.; Pizzocri, D. Journal of Nuclear Materials, Vol. 491 https://doi.org/10.1016/j.jnucmat.2017.04.039	journal	August 2017
Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation Sweet, R. T.; George, N. M.; Maldonado, G. I. Nuclear Engineering and Design, Vol. 328 https://doi.org/10.1016/j.nucengdes.2017.11.043	journal	March 2018
Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents Liu, Maolong; Brown, Nicholas R.; Terrani, Kurt A. Annals of Nuclear Energy, Vol. 110 https://doi.org/10.1016/j.anucene.2017.06.016	journal	December 2017
Cladding burst behavior of Fe-based alloys under LOCA Massey, Caleb P.; Terrani, Kurt A.; Dryepondt, Sebastien N. Journal of Nuclear Materials, Vol. 470 https://doi.org/10.1016/j.jnucmat.2015.12.018	journal	March 2016
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 TEM characterization of oxide nanoparticles in ODS Fe–12Cr–5Al alloys Unocic, Kinga A.; Pint, Bruce A.; Hoelzer, David T. Journal of Materials Science, Vol. 51, Issue 20 https://doi.org/10.1007/s10853-016-0111-5	journal	July 2016
A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding Cinbiz, M. Nedim; Brown, Nicholas R.; Terrani, Kurt A. Annals of Nuclear Energy, Vol. 109 https://doi.org/10.1016/j.anucene.2017.05.058	journal	November 2017
Experimental observations in support of the dynamic-segregation theory to explain the reactive-element effect Pint, B. A. Oxidation of Metals, Vol. 45, Issue 1-2 https://doi.org/10.1007/BF01046818	journal	February 1996
Neutron cross section sensitivity and uncertainty analysis of candidate accident tolerant fuel concepts Burns, Joseph R.; Brown, Nicholas R. Annals of Nuclear Energy, Vol. 110 https://doi.org/10.1016/j.anucene.2017.08.004	journal	December 2017
Screening of advanced cladding materials and UN–U3Si5 fuel Brown, Nicholas R.; Todosow, Michael; Cuadra, Arantxa Journal of Nuclear Materials, Vol. 462 https://doi.org/10.1016/j.jnucmat.2015.03.016	journal	July 2015
Influence of the Cr content on the permeation of hydrogen in Fe alloys Peñalva, I.; Alberro, G.; Aranburu, J. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.10.032	journal	November 2013
Hydrogen permeation in FeCrAl alloys for LWR cladding application Hu, Xunxiang; Terrani, Kurt A.; Wirth, Brian D. Journal of Nuclear Materials, Vol. 461 https://doi.org/10.1016/j.jnucmat.2015.02.040	journal	June 2015
Thermodynamics of the Zr-H System Wang, Wei-E; Olander, Donald R. Journal of the American Ceramic Society, Vol. 78, Issue 12 https://doi.org/10.1111/j.1151-2916.1995.tb07972.x	journal	December 1995
Hydrogen Permeation Through Metals, Alloys and Oxides at Elevated Temperatures Huffine, C. L.; Williams, J. M. CORROSION, Vol. 16, Issue 9 https://doi.org/10.5006/0010-9312-16.9.102	journal	September 1960
Synopsis and outcome of the QUENCH experimental program Steinbrück, M.; Große, M.; Sepold, L. Nuclear Engineering and Design, Vol. 240, Issue 7 https://doi.org/10.1016/j.nucengdes.2010.03.021	journal	July 2010
Development of a silicon carbide fibre with high tensile strength Yajima, S.; Hayashi, J.; Omori, M. Nature, Vol. 261, Issue 5562 https://doi.org/10.1038/261683a0	journal	June 1976
Synthesis of Continuous Sic Fibers with High Tensile Strength Yajima, Seishi; Okamura, Kiyohito; Hayashi, Josaburo Journal of the American Ceramic Society, Vol. 59, Issue 7-8 https://doi.org/10.1111/j.1151-2916.1976.tb10975.x	journal	July 1976
Effects of fast-neutron irradiation on pyrolytic silicon carbide Price, R. J. Journal of Nuclear Materials, Vol. 33, Issue 1 https://doi.org/10.1016/0022-3115(69)90003-8	journal	October 1969
Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects Katoh, Yutai; Ozawa, Kazumi; Shih, Chunghao Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.06.040	journal	May 2014
Irradiation-induced shrinkage of highly crystalline SiC fibers Kondo, Sosuke; Hinoki, Tatsuya; Nonaka, Makoto Acta Materialia, Vol. 83 https://doi.org/10.1016/j.actamat.2014.07.057	journal	January 2015
SiC/SiC composites through transient eutectic-phase route for fusion applications Katoh, Y.; Kohyama, A.; Nozawa, T. Journal of Nuclear Materials, Vol. 329-333, p. 587-591 https://doi.org/10.1016/j.jnucmat.2004.04.157	journal	August 2004
Design, preparation and properties of non-oxide CMCs for application in engines and nuclear reactors: an overview Naslain, R. Composites Science and Technology, Vol. 64, Issue 2 https://doi.org/10.1016/S0266-3538(03)00230-6	journal	February 2004
Thermo-mechanical properties and microstructure of silicon carbide composites fabricated by nano-infiltrated transient eutectoid process Katoh, Y.; Dong, S. M.; Kohyama, A. Fusion Engineering and Design, Vol. 61-62 https://doi.org/10.1016/S0920-3796(02)00180-1	journal	November 2002
Melt Infiltration Approach to Ceramic Matrix Composites Hillig, William B. Journal of the American Ceramic Society, Vol. 71, Issue 2 https://doi.org/10.1111/j.1151-2916.1988.tb05840.x	journal	February 1988
Development of high-strength reaction-sintered silicon carbide Suyama, S.; Kameda, T.; Itoh, Y. Diamond and Related Materials, Vol. 12, Issue 3-7 https://doi.org/10.1016/S0925-9635(03)00066-9	journal	March 2003
High-performance SiC/SiC composites by improved PIP processing with new precursor polymers Kohyama, A.; Kotani, M.; Katoh, Y. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00270-1	journal	December 2000
Handbook of SiC properties for fuel performance modeling Snead, Lance L.; Nozawa, Takashi; Katoh, Yutai Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.016	journal	September 2007
Paralinear Oxidation of CVD SiC in Water Vapor Opila, Elizabeth J.; Hann, Raiford E. Journal of the American Ceramic Society, Vol. 80, Issue 1 https://doi.org/10.1111/j.1151-2916.1997.tb02810.x	journal	January 1997
High-temperature tensile strength of near-stoichiometric SiC/SiC composites Hironaka, K.; Nozawa, T.; Hinoki, T. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01049-8	journal	December 2002
Enchanced high-temperature performances of SiC/SiC composites by high densification and crystalline structure Shimoda, Kazuya; Hinoki, Tatsuya; Kishimoto, Hirotatsu Composites Science and Technology, Vol. 71, Issue 3, p. 326-332 https://doi.org/10.1016/j.compscitech.2010.11.026	journal	February 2011
Development of Silicon Carbide Composites for Fusion Lance, L. Snead Fusion Technology, Vol. 24, Issue 1 https://doi.org/10.13182/FST93-A30175	journal	August 1993
Current status and critical issues for development of SiC composites for fusion applications Katoh, Y.; Snead, L. L.; Henager, C. H. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.032	journal	August 2007
Radiation effects in SiC for nuclear structural applications Katoh, Yutai; Snead, Lance L.; Szlufarska, Izabela Current Opinion in Solid State and Materials Science, Vol. 16, Issue 3 https://doi.org/10.1016/j.cossms.2012.03.005	journal	June 2012
Characterization of SiC–SiC composites for accident tolerant fuel cladding Deck, C. P.; Jacobsen, G. M.; Sheeder, J. Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.08.020	journal	November 2015
Fabrication and measurement of hoop strength of SiC triplex tube for nuclear fuel cladding applications Kim, Daejong; Lee, Hyun-Geun; Park, Ji Yeon Journal of Nuclear Materials, Vol. 458 https://doi.org/10.1016/j.jnucmat.2014.11.117	journal	March 2015
Stability of SiC and its composites at high neutron fluence Katoh, Yutai; Nozawa, Takashi; Snead, Lance L. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.088	journal	October 2011
Vapor-Phase Fabrication and Properties of Continuous-Filament Ceramic Composites Besmann, T. M.; Sheldon, B. W.; Lowden, R. A. Science, Vol. 253, Issue 5024 https://doi.org/10.1126/science.253.5024.1104	journal	September 1991
Fabrication of tubular SiCf/SiC using different preform architectures by electrophoretic deposition and hot pressing Fitriani, Pipit; Sharma, Amit Siddharth; Septiadi, Arifin Ceramics International, Vol. 43, Issue 10 https://doi.org/10.1016/j.ceramint.2017.03.056	journal	July 2017
Preparation of SiC/SiC Composites by Hot Pressing, Using Tyranno-SA Fiber as Reinforcement Dong, Shaoming; Katoh, Yutai; Kohyama, Akira Journal of the American Ceramic Society, Vol. 86, Issue 1 https://doi.org/10.1111/j.1151-2916.2003.tb03272.x	journal	January 2003
Development of the tailored SiC/SiC composites by the combined fabrication process of ICVI and NITE methods Shimoda, Kazuya; Hinoki, Tatsuya; Katoh, Yutai Journal of Nuclear Materials, Vol. 384, Issue 2, p. 103-108 https://doi.org/10.1016/j.jnucmat.2008.10.025	journal	February 2009
Mechanical properties of SiC/SiC braided tubes for fuel cladding Rohmer, Eric; Martin, Eric; Lorrette, Christophe Journal of Nuclear Materials, Vol. 453, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.035	journal	October 2014
Investigation of the C-ring test for measuring hoop tensile strength of nuclear grade ceramic composites Jacobsen, G. M.; Stone, J. D.; Khalifa, H. E. Journal of Nuclear Materials, Vol. 452, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.05.002	journal	September 2014
Radiation-tolerant joining technologies for silicon carbide ceramics and composites Katoh, Yutai; Snead, Lance L.; Cheng, Ting Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.002	journal	May 2014
Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures Katoh, Yutai; Snead, Lance L.; Nozawa, Takashi Journal of Nuclear Materials, Vol. 403, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.06.002	journal	August 2010
Effects of neutron irradiation on mechanical properties of silicon carbide composites fabricated by nano-infiltration and transient eutectic-phase process Koyanagi, Takaaki; Ozawa, Kazumi; Hinoki, Tatsuya Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.005	journal	May 2014
Strength of SiCf-SiCm composite tube under uniaxial and multiaxial loading Shapovalov, Kirill; Jacobsen, George M.; Alva, Luis Journal of Nuclear Materials, Vol. 500 https://doi.org/10.1016/j.jnucmat.2018.01.001	journal	March 2018
Fabrication and characterization of joined silicon carbide cylindrical components for nuclear applications Khalifa, H. E.; Deck, C. P.; Gutierrez, O. Journal of Nuclear Materials, Vol. 457 https://doi.org/10.1016/j.jnucmat.2014.11.071	journal	February 2015
Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature Koyanagi, T.; Katoh, Y.; Kiggans, J. O. Journal of Nuclear Materials, Vol. 488 https://doi.org/10.1016/j.jnucmat.2017.03.017	journal	May 2017
High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties Katoh, Yutai; Nozawa, Takashi; Shih, Chunghao Journal of Nuclear Materials, Vol. 462 https://doi.org/10.1016/j.jnucmat.2014.12.121	journal	July 2015
Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions Koyanagi, Takaaki; Katoh, Yutai Journal of Nuclear Materials, Vol. 494 https://doi.org/10.1016/j.jnucmat.2017.07.007	journal	October 2017
Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures Silva, Chinthaka M.; Katoh, Yutai; Voit, Stewart L. Journal of Nuclear Materials, Vol. 460 https://doi.org/10.1016/j.jnucmat.2015.02.002	journal	May 2015
Chemical compatibility between UO 2 fuel and SiC cladding for LWRs. Application to ATF (Accident-Tolerant Fuels) Braun, James; Guéneau, Christine; Alpettaz, Thierry Journal of Nuclear Materials, Vol. 487 https://doi.org/10.1016/j.jnucmat.2017.02.031	journal	April 2017
Safety Assessment of SiC Cladding Oxidation under Loss-of-Coolant Accident Conditions in Light Water Reactors Lee, Youho; McKrell, Thomas J.; Yue, Chao Nuclear Technology, Vol. 183, Issue 2 https://doi.org/10.13182/NT12-122	journal	August 2013
Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application Angelici Avincola, V.; Grosse, M.; Stegmaier, U. Nuclear Engineering and Design, Vol. 295 https://doi.org/10.1016/j.nucengdes.2015.10.002	journal	December 2015
Silicon carbide composite for light water reactor fuel assembly applications Yueh, Ken; Terrani, Kurt A. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.004	journal	May 2014
FABRICATION AND MATERIAL ISSUES FOR THE APPLICATION OF SiC COMPOSITES TO LWR FUEL CLADDING Kim, Weon-Ju; Kim, Daejong; Park, Ji Yeon Nuclear Engineering and Technology, Vol. 45, Issue 4 https://doi.org/10.5516/NET.07.2012.084	journal	August 2013
Corrosion Behavior of Silicon Carbide in 290oC Water Hirayama, Hideo; Kawakubo, Takashi; Goto, Akira Journal of the American Ceramic Society, Vol. 72, Issue 11 https://doi.org/10.1111/j.1151-2916.1989.tb06029.x	journal	November 1989
Pitting corrosion in CVD SiC at 300°C in deoxygenated high-purity water Henager, Charles H.; Schemer-Kohrn, Alan L.; Pitman, Stan G. Journal of Nuclear Materials, Vol. 378, Issue 1 https://doi.org/10.1016/j.jnucmat.2008.03.025	journal	August 2008
Thermodynamic and experimental study of carbon formation on carbides under hydrothermal conditions Jacobson, Nathan S.; Gogotsi, Yury G.; Yoshimura, Masahiro Journal of Materials Chemistry, Vol. 5, Issue 4 https://doi.org/10.1039/jm9950500595	journal	January 1995
Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation Terrani, K. A.; Yang, Y.; Kim, Y. -J. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.019	journal	October 2015
Correlating quartz dissolution kinetics in pure water from 25 to 625°C Tester, Jefferson W.; Worley, W. Gabriel; Robinson, Bruce A. Geochimica et Cosmochimica Acta, Vol. 58, Issue 11 https://doi.org/10.1016/0016-7037(94)90020-5	journal	June 1994
The dissolution kinetics of amorphous silica into sodium chloride solutions: effects of temperature and ionic strength Icenhower, Jonathan P.; Dove, Patricia M. Geochimica et Cosmochimica Acta, Vol. 64, Issue 24 https://doi.org/10.1016/S0016-7037(00)00487-7	journal	December 2000
Effect of dissolved hydrogen on the corrosion behavior of chemically vapor deposited SiC in a simulated pressurized water reactor environment Kim, Daejong; Lee, Hyeon-Geun; Park, Ji Yeon Corrosion Science, Vol. 98 https://doi.org/10.1016/j.corsci.2015.05.031	journal	September 2015
Hydrothermal corrosion of silicon carbide joints without radiation Koyanagi, Takaaki; Katoh, Yutai; Terrani, Kurt A. Journal of Nuclear Materials, Vol. 481 https://doi.org/10.1016/j.jnucmat.2016.09.027	journal	December 2016
Microstructure and hydrothermal corrosion behavior of NITE-SiC with various sintering additives in LWR coolant environments Parish, Chad M.; Terrani, Kurt A.; Kim, Young-Jin Journal of the European Ceramic Society, Vol. 37, Issue 4 https://doi.org/10.1016/j.jeurceramsoc.2016.11.033	journal	April 2017
Effect of irradiation damage on hydrothermal corrosion of SiC Kondo, Sosuke; Lee, Moonhee; Hinoki, Tatsuya Journal of Nuclear Materials, Vol. 464 https://doi.org/10.1016/j.jnucmat.2015.04.034	journal	September 2015
Viability of Hydrogen Water Chemistry for Protecting In-Vessel Components of Boiling Water Reactors Macdonald, D. D. CORROSION, Vol. 48, Issue 3 https://doi.org/10.5006/1.3315925	journal	March 1992
Role of irradiation-induced defects on SiC dissolution in hot water Kondo, Sosuke; Mouri, Shinichiro; Hyodo, Yoshihiro Corrosion Science, Vol. 112 https://doi.org/10.1016/j.corsci.2016.08.007	journal	November 2016
Long-term corrosion behavior of CVD SiC in 360°C water and 400°C steam Park, Jeong-Yong; Kim, Il-Hyun; Jung, Yang-Il Journal of Nuclear Materials, Vol. 443, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.07.058	journal	November 2013
Characteristics of Composite Silicon Carbide Fuel Cladding after Irradiation under Simulated PWR Conditions Stempien, John D.; Carpenter, David M.; Kohse, Gordon Nuclear Technology, Vol. 183, Issue 1 https://doi.org/10.13182/NT12-86	journal	July 2013
Re-defining failure envelopes for silicon carbide composites based on damage process analysis by acoustic emission Nozawa, Takashi; Ozawa, Kazumi; Tanigawa, Hiroyasu Fusion Engineering and Design, Vol. 88, Issue 9-10 https://doi.org/10.1016/j.fusengdes.2013.05.054	journal	October 2013
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
A structural model for multi-layered ceramic cylinders and its application to silicon carbide cladding of light water reactor fuel Lee, Youho; Kazimi, Mujid S. Journal of Nuclear Materials, Vol. 458 https://doi.org/10.1016/j.jnucmat.2014.12.013	journal	March 2015
Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding Stone, J. G.; Schleicher, R.; Deck, C. P. Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.08.001	journal	November 2015
Mechanical performance of SiC three-layer cladding in PWRs Angelici Avincola, Valentina; Guenoun, Pierre; Shirvan, Koroush Nuclear Engineering and Design, Vol. 310 https://doi.org/10.1016/j.nucengdes.2016.10.008	journal	December 2016
Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis Singh, Gyanender; Terrani, Kurt; Katoh, Yutai Journal of Nuclear Materials, Vol. 499 https://doi.org/10.1016/j.jnucmat.2017.11.004	journal	February 2018
Recent research and development for the dual-coolant blanket concept in the US Morley, N. B.; Katoh, Y.; Malang, S. Fusion Engineering and Design, Vol. 83, Issue 7-9 https://doi.org/10.1016/j.fusengdes.2008.04.012	journal	December 2008
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 Singh, G.; Sweet, R.; Brown, N. R. Journal of Nuclear Materials, Vol. 499 https://doi.org/10.1016/j.jnucmat.2017.10.059	journal	February 2018
Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux Petrie, Christian M.; Koyanagi, Takaaki; McDuffee, Joel L. Journal of Nuclear Materials, Vol. 491 https://doi.org/10.1016/j.jnucmat.2017.04.058	journal	August 2017
Evaluating the irradiation effects on the elastic properties of miniature monolithic SiC tubular specimens Singh, G.; Koyanagi, T.; Petrie, C. Journal of Nuclear Materials, Vol. 499 https://doi.org/10.1016/j.jnucmat.2017.10.060	journal	February 2018
SiC Recession Caused by SiO ₂ Scale Volatility under Combustion Conditions: II, Thermodynamics and Gaseous-Diffusion Model Opila, Elizabeth J.; Smialek, James L.; Robinson, Raymond C. Journal of the American Ceramic Society, Vol. 82, Issue 7 https://doi.org/10.1111/j.1151-2916.1999.tb02005.x	journal	July 1999
Oxidation and Volatilization of Silica Formers in Water Vapor Opila, Elizabeth J. Journal of the American Ceramic Society, Vol. 86, Issue 8 https://doi.org/10.1111/j.1151-2916.2003.tb03459.x	journal	August 2003
Observations of Accelerated Silicon Carbide Recession by Oxidation at High Water-Vapor Pressures More, Karren L.; Tortorelli, Peter F.; Ferber, Mattison K. Journal of the American Ceramic Society, Vol. 83, Issue 1 https://doi.org/10.1111/j.1151-2916.2000.tb01172.x	journal	January 2000
High-Temperature Stability of SiC-Based Composites in High-Water-Vapor-Pressure Environments More, Karren L.; Tortorelli, Peter F.; Walker, Larry R. Journal of the American Ceramic Society, Vol. 86, Issue 8 https://doi.org/10.1111/j.1151-2916.2003.tb03463.x	journal	August 2003
Steam oxidation of fuel in defective LWR rods Olander, D. R.; Soo Kim, Yeon; Wang, Wei-E Journal of Nuclear Materials, Vol. 270, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00759-4	journal	April 1999
A conceptual model for the fuel oxidation of defective fuel Higgs, J. D.; Lewis, B. J.; Thompson, W. T. Journal of Nuclear Materials, Vol. 366, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2006.12.050	journal	June 2007
Materials chemistry and transport modeling for severe accident analyses in light-water reactors III. Fuel dissolution by molten cladding Olander, D. R. Nuclear Engineering and Design, Vol. 162, Issue 2-3 https://doi.org/10.1016/0029-5493(95)01130-7	journal	April 1996
Oxidation behavior of U-Si compounds in air from 25 to 1000 C Sooby Wood, E.; White, J. T.; Nelson, A. T. Journal of Nuclear Materials, Vol. 484 https://doi.org/10.1016/j.jnucmat.2016.12.016	journal	February 2017
Degradation of UN and UN–U ₃ Si ₂ pellets in steam environment Lopes, Denise Adorno; Uygur, Selim; Johnson, Kyle Journal of Nuclear Science and Technology, Vol. 54, Issue 4 https://doi.org/10.1080/00223131.2016.1274689	journal	January 2017
Motivation for utilizing new high-performance advanced materials in nuclear energy systems Zinkle, S. J.; Terrani, K. A.; Snead, L. L. Current Opinion in Solid State and Materials Science, Vol. 20, Issue 6 https://doi.org/10.1016/j.cossms.2016.10.004	journal	December 2016
An approach to fuel development and qualification Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.029	journal	September 2007
Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis Farmer, M. T.; Bunt, R.; Corradini, M. Nuclear Science and Engineering, Vol. 184, Issue 3 https://doi.org/10.13182/NSE16-13	journal	November 2016

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