An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions

Gamble, Kyle A.; Barani, Tommaso; Pizzocri, David; Hales, Jason D.; Terrani, Kurt A.; Pastore, Giovanni

doi:10.1016/j.jnucmat.2017.04.039

Title: An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions

Journal Article · Sun Apr 30 00:00:00 EDT 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.04.039· OSTI ID:1357974

Gamble, Kyle A. ^[1]; Barani, Tommaso ^[2]; Pizzocri, David ^[2]; Hales, Jason D. ^[1]; Terrani, Kurt A. ^[3]; Pastore, Giovanni ^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)
Politecnico di Milano, Milano (Italy)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Iron-chromium-aluminum (FeCrAl) alloys are candidates to be used as nuclear fuel cladding for increased accident tolerance. An analysis of the response of FeCrAl under normal operating and loss of coolant conditions has been performed using fuel performance modeling. In particular, recent information on FeCrAl material properties and phenomena from separate effects tests has been implemented in the BISON fuel performance code and analyses of integral fuel rod behavior with FeCrAl cladding have been performed. BISON simulations included both light water reactor normal operation and loss-of-coolant accidental transients. In order to model fuel rod behavior during accidents, a cladding failure criterion is desirable. For FeCrAl alloys, a failure criterion is developed using recent burst experiments under loss of coolant like conditions. The added material models are utilized to perform comparative studies with Zircaloy-4 under normal operating conditions and oxidizing and non-oxidizing out-of-pile loss of coolant conditions. The results indicate that for all conditions studied, FeCrAl behaves similarly to Zircaloy-4 with the exception of improved oxidation performance. Further experiments are required to confirm these observations.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)

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

Grant/Contract Number:: AC05-00OR22725; AC07-05ID14517

OSTI ID:: 1357974

Alternate ID(s):: OSTI ID: 1397861; OSTI ID: 1414381

Report Number(s):: INL/JOU-16-40643; AF5810000; NEAF278

Journal Information:: Journal of Nuclear Materials, Vol. 491, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 81 works

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References (19)

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
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
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
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
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
Validating the BISON fuel performance code to integral LWR experiments Williamson, R. L.; Gamble, K. A.; Perez, D. M. Nuclear Engineering and Design, Vol. 301 https://doi.org/10.1016/j.nucengdes.2016.02.020	journal	May 2016
An object-oriented finite element framework for multiphysics phase field simulations Tonks, Michael R.; Gaston, Derek; Millett, Paul C. Computational Materials Science, Vol. 51, Issue 1 https://doi.org/10.1016/j.commatsci.2011.07.028	journal	January 2012
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
Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions Wu, Xu; Kozlowski, Tomasz; Hales, Jason D. Annals of Nuclear Energy, Vol. 85 https://doi.org/10.1016/j.anucene.2015.06.032	journal	November 2015
Accident-Tolerant-Fuel Performance Analysis of APMT Steel Clad/UO ₂ Fuel and APMT Steel Clad/UN-U ₃ Si ₅ Fuel Concepts Galloway, Jack; Unal, Cetin Nuclear Science and Engineering, Vol. 182, Issue 4 https://doi.org/10.13182/NSE15-7	journal	April 2016
The proper use of thermal expansion coefficients in finite element calculations Niffenegger, Markus; Reichlin, Klaus Nuclear Engineering and Design, Vol. 243 https://doi.org/10.1016/j.nucengdes.2011.12.006	journal	February 2012
Oxidation growth stresses in an alumina-forming ferritic steel measured by creep deflection Saunders, S. R. J.; Evans, H. E.; Li, M. Oxidation of Metals, Vol. 48, Issue 3-4 https://doi.org/10.1007/BF01670498	journal	October 1997
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
Transformation kinetics of alloys under non-isothermal conditions Massih, A. R.; Jernkvist, L. O. Modelling and Simulation in Materials Science and Engineering, Vol. 17, Issue 5 https://doi.org/10.1088/0965-0393/17/5/055002	journal	May 2009
The TRANSURANUS mechanical model for large strain analysis Di Marcello, Valentino; Schubert, Arndt; van de Laar, Jacques Nuclear Engineering and Design, Vol. 276 https://doi.org/10.1016/j.nucengdes.2014.04.041	journal	September 2014
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling Pastore, Giovanni; Swiler, L. P.; Hales, J. D. Journal of Nuclear Materials, Vol. 456 https://doi.org/10.1016/j.jnucmat.2014.09.077	journal	January 2015
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS Barani, T.; Bruschi, E.; Pizzocri, D. Journal of Nuclear Materials, Vol. 486 https://doi.org/10.1016/j.jnucmat.2016.10.051	journal	April 2017
LIFE-II — A computer analysis of fast-reactor fuel-element behavior as a function of reactor operating history Jankus, V. Z.; Weeks, R. W. Nuclear Engineering and Design, Vol. 18, Issue 1 https://doi.org/10.1016/0029-5493(72)90038-6	journal	January 1972
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

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