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Improving Nuclear Power Plant Safety with FeCrAl Alloy Fuel Cladding

Published online by Cambridge University Press:  09 January 2017

Raul B. Rebak ,
Kurt A. Terrani ,
William P. Gassmann ,
John B. Williams  and
Kevin L. Ledford
Raul B. Rebak*
Affiliation:
GE Global Research, 1 Research Circle, CEB2551, Schenectady, NY12309, U.S.A.
Kurt A. Terrani
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN37831
William P. Gassmann
Affiliation:
Exelon Generation, Kennett Square, PA19348
John B. Williams
Affiliation:
Southern Nuclear, Chelsea, AL35043
Kevin L. Ledford
Affiliation:
Global Nuclear Fuels Americas, Wilmington NC28401
*
*(Email: [email protected])

Abstract

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The US Department of Energy (DOE) is partnering with fuel vendors to develop enhanced accident tolerant nuclear fuels for Generation III water cooled reactors. In comparison with the standard current uranium dioxide and zirconium alloy system UO2-Zr), the proposed alternative accident tolerant fuel (ATF) should better tolerate loss of cooling in the core for a considerably longer time while maintaining or improving the fuel performance during normal operation conditions. General Electric, Oak Ridge National Laboratory and their partners have proposed to replace zirconium based alloy cladding in current commercial power reactors with an iron-chromium-aluminum (FeCrAl) alloy cladding such as APMT. The use of FeCrAl alloys will greatly reduce the risk of operating the power reactors to produce electricity.

Keywords

corrosionenergy generationnuclear materials
Type
Articles
Information
MRS Advances , Volume 2 , Issue 21-22: Energy and Sustainability , 2017 , pp. 1217 - 1224
Copyright
Copyright © Materials Research Society 2017 

References

REFERENCES

Rebak, R. B., “Nuclear Application of Oxide Dispersion Strengthened and Nano-Featured Alloys: An Introduction, JOM, Vol. 66, No. 12, pp. 2424–2426 (2014)Google Scholar
US Nuclear Regulatory Commission, Fact Sheet on Nuclear Reactor Risk, http://www.nrc.gov/reading-rm/doc-collections/fact-sheets/reactor-risk.html Google Scholar
Sridhar, N., “Risk Assessment of Corrodible Systems—An Overview,” Materials Performance, June 2011, p. 32.Google Scholar
IAEA, International Atomic Energy Agency, “Risk management: A tool for improving nuclear power plant performance,” TECDOC-1209, Vienna, 2001 Google Scholar
Zinkle, S. J., Terrani, K. A., Gehin, J. C., Ott, L. J., and Snead, L. L., “Accident tolerant fuels for LWRs: A perspective,” Journal of Nuclear Materials, 448 (2014) 374–379 Google Scholar
Rebak, R. B., “Alloy Selection for Accident Tolerant Fuel Cladding in Commercial Light Water Reactors,” Metallurgical and Materials Transactions E, Vol. 2E, 197–207 (December 2015).Google Scholar
Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., Montgomery, R., and Carmack, W. J., Metrics for the Technical Performance Evaluation of Light Water Reactor Accident Tolerant Fuel, Nuclear Technology, 195(2), p. 111–123, August 2016.Google Scholar
Robb, K. R., “Analysis of the FeCrAl Accident Tolerant Fuel Concept Benefits During BWR Station Blackout Accidents,” Proc. of NURETH-16, Chicago, IL, USA, August 30-September 4, 2015 Google Scholar
EPRI, Electric Power Research Institute, Evaluation of Expected Behavior of LWR Stainless Steel-Clad Fuel in Long-Term Dry Storage, EPRI, Palo Alto, CA: 1996. TR-106440 Google Scholar
Rebak, R. B., Brown, N. R., and Terrani, K. A., “Assessment of Advanced Steels as Accident Tolerant Fuel Cladding for Commercial Light Water Reactors,” Paper 227, 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, August 9-12, 2015, Ottawa, Ontario, Canada (Canadian Nuclear Society, Toronto).Google Scholar
Ellis, D. D., and Rebak, R. B., “Passivation Characteristics of Ferritic Stainless Materials in Simulated Reactor Environments,” Paper C2016-7452, Corrosion/2016 (NACE International, Houston, TX).Google Scholar
Kim, Y.-J., Wagenbaugh, F., Jurewicz, T. B., Blair, R. J., and Rebak, R. B., “Environmental Behavior of Light Water Reactor Accident Tolerant Candidate Cladding Materials under Design Conditions,” Paper C2015-5817, Corrosion/2015 (NACE International, Houston, TX)Google Scholar
Rebak, R. B., and Huang, S., “Anticipated Improved Performance of Advanced Steel Cladding Under Long Term Dry Storage of Spent Fuel,” Paper No. PVP2015-45643, pp. V007T07A042; 7 pages, doi: 10.1115/PVP2015-45643 (ASME 2015)Google Scholar
George, N. M., Terrani, K., Powers, J., Worrall, A., and Maldonado, I., “Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors,” Annals of Nuclear Energy, 75 (2015) 703–712 CrossRefGoogle Scholar
Rebak, R. B. and Kim, Y.-J., “Hydrogen Diffusion in FeCrAl Alloys for Light Water Reactors Cladding Applications” Paper PVP2016-63164, 2016 ASME PVP Conference, MF-7 Materials and Technologies for Nuclear Power Plants, 17–21 July 2016, Vancouver, BC.Google Scholar