High temperature steam corrosion of cladding for nuclear applications

Experimental

Kevin M. McHugh, John E. Garnier, Sergey Rashkeev, Michael V. Glazoff, George W. Griffith, Shannon M. Bragg-Sitton

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Citations (Scopus)

Abstract

Stability of cladding materials under off-normal conditions is an important issue for the safe operation of light water nuclear reactors. Metals, ceramics, and metal/ceramic composites are being investigated as substitutes for traditional zirconium-based cladding. To support down-selection of these advanced materials and designs, a test apparatus was constructed to study the onset and evolution of cladding oxidation, and deformation behavior of cladding materials, under loss-of-coolant accident scenarios. Preliminary oxidation tests were conducted in dry oxygen and in saturated steam/air environments at 1000°C. Tube samples of Zr-702, Zr-702 reinforced with 1 ply of a β-SiC CMC overbraid, and sintered β-SiC were tested. Samples were induction heated by coupling to a molybdenum susceptor inside the tubes. The deformation behavior of Hepressurized tubes of Zr-702 and SiC CMC-reinforced Zr-702, heated to rupture, was also examined.

Original languageEnglish
Title of host publicationCeramic Engineering and Science Proceedings
Pages149-160
Number of pages12
Volume34
Edition9
Publication statusPublished - 15 Jan 2014
Externally publishedYes
EventCeramic Materials for Energy Applications III - 37th International Conference on Advanced Ceramics and Composites, ICACC 2013 - Daytona Beach, FL, United States
Duration: 27 Jan 20131 Feb 2013

Other

OtherCeramic Materials for Energy Applications III - 37th International Conference on Advanced Ceramics and Composites, ICACC 2013
CountryUnited States
CityDaytona Beach, FL
Period27/1/131/2/13

Fingerprint

Steam
Corrosion
Cermets
Oxidation
Temperature
Loss of coolant accidents
Light water reactors
Molybdenum
Zirconium
Oxygen
Composite materials
Air

ASJC Scopus subject areas

  • Ceramics and Composites
  • Materials Chemistry

Cite this

McHugh, K. M., Garnier, J. E., Rashkeev, S., Glazoff, M. V., Griffith, G. W., & Bragg-Sitton, S. M. (2014). High temperature steam corrosion of cladding for nuclear applications: Experimental. In Ceramic Engineering and Science Proceedings (9 ed., Vol. 34, pp. 149-160)

High temperature steam corrosion of cladding for nuclear applications : Experimental. / McHugh, Kevin M.; Garnier, John E.; Rashkeev, Sergey; Glazoff, Michael V.; Griffith, George W.; Bragg-Sitton, Shannon M.

Ceramic Engineering and Science Proceedings. Vol. 34 9. ed. 2014. p. 149-160.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

McHugh, KM, Garnier, JE, Rashkeev, S, Glazoff, MV, Griffith, GW & Bragg-Sitton, SM 2014, High temperature steam corrosion of cladding for nuclear applications: Experimental. in Ceramic Engineering and Science Proceedings. 9 edn, vol. 34, pp. 149-160, Ceramic Materials for Energy Applications III - 37th International Conference on Advanced Ceramics and Composites, ICACC 2013, Daytona Beach, FL, United States, 27/1/13.
McHugh KM, Garnier JE, Rashkeev S, Glazoff MV, Griffith GW, Bragg-Sitton SM. High temperature steam corrosion of cladding for nuclear applications: Experimental. In Ceramic Engineering and Science Proceedings. 9 ed. Vol. 34. 2014. p. 149-160
McHugh, Kevin M. ; Garnier, John E. ; Rashkeev, Sergey ; Glazoff, Michael V. ; Griffith, George W. ; Bragg-Sitton, Shannon M. / High temperature steam corrosion of cladding for nuclear applications : Experimental. Ceramic Engineering and Science Proceedings. Vol. 34 9. ed. 2014. pp. 149-160
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